INTRODUCTION Paul Govaerts, general manager
A new mission
SCK•CEN has been founded in 1952 to support the launching of nuclear scientific and industrial activities in Belgium. An important scientific research infrastructure and manpower covered a comprehensive programme on the development of the nuclear fuel cycle. In 1991 our mission has been focused on the safety aspects of this cycle. Last year the board of governors approved a shift, confirming the "de facto" situation. More attention has to be given to non-energetic problems related to ionizing radiation, such as medical applications and the impact of natural radiation, as well on earth as in space. Moreover, a concerted action on knowledge management, training and education must become clearly visible in our work plan.
Training and education are of major importance
A new strategy
The strategic exercise which has been started in 2003 identified following research priorities: The safety of current reactors: in particular problems related to fuel, structural materials and core physics in light–water reactors; A contribution to the development of new fuel cycle concepts, in particular the demonstration of an accelerator driven system for the transmutation of long-lived waste and the mastering of lead coolant technology; A contribution to the international fusion research effort, the study of materials problems using the BR2 test reactor, instrumentation, waste and safety problems; The demonstration of the feasibility of the evacuation of several kinds of conditioned radioactive waste to a geological clay layer; The safe and cost-effective decommissioning of nuclear facilities; The preserving of nuclear chemistry know-how; A contribution to the global effort on the understanding of biological effects of ionizing radiation and the preserving of the capability to perform comprehensive retrospective assessments; Technical and scientific support to emergency planning and response and safeguards; Medical applications of ionizing radiation, in particular the production of the raw sources for radioisotopes, radiological optimization of interventions and the study of unwanted aspects of radiotherapies; The social integration of nuclear problems: the practical implementation of the precautionary principle, radiation protection ethics, risk communication, stakeholder's involvement,...
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
Those activities have to be supported by an up-to-date safe and reliable research infrastructure, such as the BR2 materials testing reactor, the underground research laboratory and the hot-cells. The accumulated know-how has to be stored and transferred by adequate techniques.
Research infrastructure is important: the BR2 materials testing reactor will be kept in a safe and reliable condition at least until 2016. From then on, MYRRHA can take over.
An on-going technology assessment
The decisions on energy production and conversion are of ultimate importance for our current and future way of living. Discussions on the impact of geopolitics on supply assurance, the global warming of our planet, the risks of proliferation and nuclear and radiological terrorism, and the economic impact of fuel prices can be found daily in all kinds of press media. Due to historical reasons (the original sin of Hiroshima, Nagasaki and the mortal sin of Chernobyl) the call for nuclear energy requires a continuous assessment process. Those evaluations relate to technological, economical, ecological and safety aspects. SCK•CEN has the ambition to mobilize its comprehensive know how based on scientific insights to the public discussion on the global-cost effectiveness of nuclear energy.
To keep research facilities available
The board of governors decided to keep the BR2 materials testing reactor in a safe and reliable condition at least until 2016, when the license requires a new safety review, subsequent of this of 2006 (an intermediate review is imposed for 2011). Two major problems will have to be tackled: the build-up of antireactivity by helium-3 in the beryllium reflector and the conversion to low-enriched fuel, preserving the high-power density. The strategic plan retained the accelerator driven demo MYRRHA as a new research facility with a fast neutron spectrum, which is required for the development of new reactor concepts. Preparing a business plan and partner- and sponsorship for this seducing facility, we play a dominant role within the European Eurotrans project. Besides those long lasting discussions, SCK•CEN is showing its openness to international networking by stimulating several European networks of excellence, having access to pooled facilities, and by an abundant number of bilateral agreements.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
SCK•CEN ORGANISATIONAL CHART
Chairman of the Board
Frank Deconinck
General Manager
Paul Govaerts
Programme Managers Fusion: Marc Decréton Radioactive Waste & Clean-up: Guy Collard Radiation Protection: Mark Loos Reactor Safety: Pierre D'hondt Social-economical Aspects: Gilbert Eggermont Medical Applications: Mark Loos Scientific Training: Frans Moons Safety Training: Frank Joppen
Advisor Medical Service Gilbert Eggermont Luc Holmstock Quality Assurance Health Physics & Safety Peter De Regge Department Contracts Frank Joppen Ludo Veuchelen Safety EURIDICE Scientific Co-ordinator Marc Buyens Frans Moons Fusion Marc Decréton
Radiation Reactor Radioactive Reactor BR2 Technical Personnel, Marketing & Protection Safety Waste & Services Finances & Public Relations Clean-Up Administration
Mark Pierre D'hondt Guy Pol Jan Christian Jef Loos Collard Gubel Van der Auwera Legrain Vanwildemeersch
Safeguards & Reactor Physics Nuclear BR2 Operation Budget, Purchase Physics & MYRRHA Chemistry & Pol & Information Measurements Hamid Services Gubel systems Klaas Aït Abderrahim Léon Pierre van der Meer Vandevelde Reactor Van Doorslaer Reactor Experiments Low-level Materials Sit Restoration Jean Radioactive Research Luc Dekeyser Measurements Eric Noynaert Christian Van Walle Hurtgen Waste & Instrumentation Disposal Radiation Francis Geert Protection Berghmans Volckaert Research Hans Vanmarcke R&D Valorisation Decision Vincent Strategy Massaut Research Frank Hardeman
RADIATION PROTECTION DIVISION Mark Loos
Supporting Staff Els Van Musscher
Safeguards and Physics Measurements Department
Scientific Staff Jean-Pierre Alzetta, Reinhard Boons, Michel Bruggeman, Michèle Coeck, Wim de Boeck, Jean-Louis Genicot, Jozef Gerits, Olivier Goossens, Anne Laure Lebacq, Ludo Maes, Ludo Melis, Emiel Mertens, Kristien Smans, Liesel Sneyers, Lara Struelens, Dirk Vanbeckhoven, Klaas van der Meer, Filip Vanhavere, Peter Vermaercke, Paul Willeborts.
Supporting Staff Veronique Cornelissen, August Daemen, Eddy Daniëls, Ingrid Geboers, Guido Hooyberghs, Bart Marlein, Kris Paepen, Ludo Van de Velde, Jan Vandoninck, Mark Van Iersel, Viviane Vanspringel, Marc Vreys.
Low-level Radioactivity Measurements Department
Scientific Staff Edmond Dupuis, Christian Hurtgen, Freddy Verrezen.
Supporting Staff Benny Bouwens, Sandy Cools, Karin Jacobs, Linde Jansen, Hilde Loots, Betty Ruts, Willeke Van Baelen, Betty Vandingelen, Mady Van Lommel, Mieke Vanuytven, Bart Vennekens, Myriam Verbist, René Verkoyen, Diana Verstrepen.
Radiation Protection Research Department
Scientific Staff Iris Adriaens, Sarah Baatout, Rafi Benotmane, Hanane Derradji, Louis de Saint-George, Lise Duquene, Luc Holmstock, Paul Jaquet, Max Mergeay, Arlette Michaux, Marcella Mori, Geert Olyslaegers, Johan Paridaens, Anne Straczek, Lieve Sweeck, Yves Thiry, Hildegarde Vandenhove, May Van Hees, Hans Vanmarcke, Eric Van Mieghem, Ingrid Van Regenmortel, Joris Verheyde, Caroline Vincke, Theo Zeevaert.
Supporting Staff Paul Bens, Jasmine Buset, Mieke Neefs, Werner Schoonjans, Jef Sannen, Els Tessens, Emiel Van Bogaert, Jean Wannijn.
Decision Strategy Research and Policy Support Department
Scientific Staff Michel Bovy, Benny Carlé, Isabelle Fucks, Frank Hardeman, Carlos Rojas Palma, Jan Ruts, Alain Sohier, Catrinel Turcanu.
Supporting Staff René Bubbe, Swat Janssens, Guy Van Sanden.
Internal Service for the Protection and Prevention of Workers
Scientific Staff Philippe Antoine, Francis Chody, Simon Claes, Pascal Deboodt, Freddy Geenen, Willy Geenen, Leo Geerts, Sabine Janssens, Frank Joppen, Eric Laes, Maria Leijssens, Isabelle Maikowski, Gaston Meskens, Robby Nijs, Peter Van de Velde, Karel Van Eyndhoven, Fernand Vermeersch, Gilbert Werelds.
Supporting Staff Raf Aarts, Johan Berghmans, Patrick Bervoets, Rony Bogaerts, Filip Borgers, Kris Bruns, Dieter Danois, Eddy Fierens, Danny Geerinckx, Henri Maussen, Herman Mertens, Paul Penasse, François Poorters, Jan Sannen, Gunter Smets, Patrick Smeyers, Wilfried Smolders, Paul Van Baelen, Marc Van Bijlen, Jacky Vandersteen, Luc Vandevijvere, Philippe Vandycke, Jozef Vangheel, Davy Vanheukelen, Robert Vanhoudt, Pieter Van Lommel, Marc Van Nuffel, Cindy Verachtert, Gerard Verherstraeten, Benny Vullings. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
RADIATION PROTECTION: INTRODUCTION Mark Loos
Introduction
2004 was a year of strategic reflection. A broad discussion was organised, as well between SCK•CEN members as with external advisors. We verified our work in the field of radiation protection, we reflected on what we should do and concluded what we will do.
The main conclusion was that we have to continue to aquire a broad basic knowledge in all fields of expertise in radiation protection and to try to excel in a few well chosen domains.
Life Policy Medical sciences Support applications
Education Training Broad basic knowledge in every field of radiation protection
As a result we will continue to perform research on measuring (see GPS-based handheld device for mapping contaminated areas) (see: Determination of uranium in urine and water samples) and dosimetry techniques (see: Individual monitoring in mixed neutron/photon fields), radiobiology, microbiology (see The MOBILASATSIA experience), radioecology (see Recycling of uranium by a perennial vegetation), radiological evaluation (see Biosphere models for deep waste disposal), decision aiding systems and policy support.
Three priority research themes were defined: Life sciences, policy support and medical applications.
Life sciences
Knowledge on the biological impact of ionising radiation on man and on the behaviour of radioactive substances in the environment is essential for SCK•CEN to remain a reference for radiation protection in Belgium. This knowledge must be based on state of the art research (see irradiation and papillomavirus E2 proteins on Hela Cells ...), embedded in European and international programmes. We focus on the effects of ionising radiation on the developing organism (see Measuring chromosomal ends of X-irradiated embryos) and on the issues related to enhanced natural radioactivity (see Coal-Fired Power Plant: airborne routine discharges). Also case studies involving retrospective analysis, such as epidemiological evaluations, will get increased attention. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
Policy support
SCK•CEN wants to remain a strong partner of the Belgian authorities, particularly concerning nuclear crisis management (see: Stakeholder involvement for countermeasures in the food chain) and concerning the safeguarding of strategic nuclear materials. Hardware and software tools for decision aiding are regularly adapted to technical evolution (see: Multi criteria decision analysis on a waste repository in Mol). New systems for non-destructive radioactivity measurements of nuclear waste and spent fuel will be developed. The key actors at SCK•CEN in nuclear emergency preparedness and response receive continued training to be prepared for a quick and professional intervention. The development and research programmes on policy support are embedded in international programmes of the European Union (see: A prototype for data and information exchange - MODEM) and of the International Atomic Energy Agency, in consultation with the Belgian authorities.
Medical applications
The expertise existing at SCK•CEN will be used for the lasting improvement of nuclear and radiological techniques in medicine. We will study medical radiation protection issues in fields that are defined together with university hospitals such as the possibility to apply the ALARA (exposure As Low As Reasonably Achievable) principle in relation to image quality or desired effect (see: Image quality in vascular radiology). We will continue the production of radionuclides for nuclear medicine and the investigation of individual radiosensitivity of patients and the study of unwanted biological effects.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
DETERMINATION OF URANIUM IN URINE AND WATER SAMPLES
Background Monitoring the internal contamination of workers professionally exposed to uranium or other sources of radioactive products has been one of the concerns of radiation protection for over half a century. In the last decade, due to several global conflict situations, this concern was expanded also to members of the population none or semi professionally exposed to uranium contamination (e.g. use of depleted uranium ammunition in war zones near civil or military installations). A rapid, high precision and highly sensitive measurement technique allowing for high sample throughput is therefore needed. TR-KPA (Time Resolved Kinetic Phosphorescence Analysis) is such a technique. It allows for the measurement of small amounts of uranium (down to 0.1 µg/L) with good precision and accuracy (less than 20 % expanded uncertainty) in a great variety of sample matrices (water samples, urine samples, blood samples).
Objectives The main objective for SCK•CEN'sanalytical laboratories of the Department of Low Level Radioactivity Measurements (LRM) was to replace the existing measurement technique for uranium in urine samples (alkaline fusion, followed by fluorimetric determination) by the TR-KPA technique to improve the reliability of the analytical results and to lower the limit of quantification (from 1 µg/L for the fluorimetric method to 0.1 µg/L for the TR-KPA technique). The implementation of the TR-KPA technique was therefore extensively validated, especially concerning the sample preparation and the relevant parameters such as linearity, limit of detection, precision, accuracy, reproducibility, repeatability and robustness.
Principal results
The instrumentation used for the measurement of uranium in urine and water samples: to the left the Gilson Model 223 Sample Changer Robot on top of the KPA-11 Kinetic Phosphorescence Analyzer, in the centre the Gilson Model 402 Syringe Pump and to the right the data acquisition computer with the KPAWin V1.2.8. software.
Sample preparation has been shown to be the most important aspect in measurement performance and the major source of measurement uncertainty (about 15% absolute contribution to the expanded uncertainty for the 95% confidence level). Based on the present validation study, the optimal sample preparation conditions are: two replicates of 2 mL each to be prepared and measured independently for every sample to be analyzed (the mean value is used for the final result if standard deviation between individual results is less then rejection criterion); repeated wet ashing using concentrated nitric acid and hydrogen peroxide, followed by evaporation to dryness (using glass vials) until residue is pale yellow or white; calcination of residue in microwave oven for 60 minutes at 450 °C; dissolution of residue in 2 mL of 1 M HNO3 and measurement by TR-KPA.
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The second most important source of uncertainty, especially for the low concentrations in the region from limit of quantification to a few µg/L, is the associated uncertainty on the calibration curve and the background measurement used for background correction (about 5-10% absolute contribution to the expanded uncertainty for the 95% confidence level). Other sources of uncertainty have been defined as uncertainties on the volumetric manipulations and the uncertainty on the certified concentrations on the reference solutions used for calibration. However, their contribution to the overall uncertainty (< 20 %) can be considered neglectable.
120% In sample preparation, the calcination temperature applied in 100% the microwave furnace proves to be one of the major contributing parameters affecting the chemical
) 80%
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m CALCINATION e CONDITIONS Ch 40%
20% INADEQUATE INADEQUATE CALCINATION RECOVERY 0% 250 300 350 400 450 500 550 600
Calcination Temperature (°C10)00000
Sample The principle of operation of Time Resolved 100000 Kinetic Phosphorescence Analysis (TR-KPA): Reference excitation of the uranium/URAPLEX species in 10000 solution using 425 nm laser light, monitoring the y t decay dynamics of the excitons by measuring the i ns e
t 1000 intensity of the emitted light (at 512 nm) in the 5 n I Time window used for to 50 µs time window after excitation and Log Least Squares Fit: comparing the decay characteristics and 100 45 Time Gates (5-49) Slope, proportional with intensities with those of the reference solutions. decay constant τ
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1 549 020406080100120 Time (in "Time Gate"-units of 13 µs each)
Future developments In the near future attempts will be made to further lower the limit of quantification, to improve the measurement uncertainty and to investigate the effects of possible interferences in the biological samples that might be caused by the food habits of the people being monitored or their intake of medication.
Main contact person Christian Hurtgen, [email protected]
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
GPS-BASED HANDHELD DEVICE FOR MAPPING CONTAMINATED AREAS
Background Sometimes one is confronted with the challenge to map large areas with enhanced radioactivity. Examples are mine tailings or waste rock piles, deposits of the phosphate industry, flooding zones contaminated by effluents of plants processing ores containing enhanced natural radiation, nuclear accident sites etc. Car borne measuring equipment is not always an option, as the terrain might be rough and only accessible on foot. Airborne mapping with helicopters on the other hand is fast, but expensive, not readily available, shows difficulties with complex topography and lacks the necessary detail.
Objectives The objective was to create a portable and easily useable tool for the real time logging of radiation and location data, allowing mapping the radioactivity by simply walking over any kind of terrain with the portable equipment and post processing the data in the office. We also assessed the performance of the GPS based system on contaminated sites with areas varying from less than a hectare to several tens of hectares, with respect to speed, precision and ease of use.
Principal results
Portable equipment for mapping radioactively contaminated areas. The small GPS device, mounted on the cap on the head of the operator, transmits GPS positional data to a pocket PC (PPC), attached to the handheld gamma detector. The gamma detector sends doserates to the PPC, creating a data log that can be post processed to obtain a map of the radioactive contamination.
Alternately, the serial data output of a standard portable gamma detector and of a small GPS device are transmitted wirelessly to a pocket PC (PPC). The operator carries the gamma detector, Pocket PC the GPS and the PPC around over the terrain (see figure), hence in situ creating a data log suited for post processing at the office. The time difference γ-detector between position and radiation readout is never more than 1 s, which is acceptable considering the low moving speed of an operator on foot. The sampling period can be varied and has a minimum of 2 seconds, which allows changing the spatial density of the data points.
The data logging software was home made. The intrinsic positional precision of the system was found to be 5 to 10 m. It was derived by mapping a small area with a well known contamination. The system is easy to handle and relatively fast in use: about 45 hectares of very rough terrain were adequately mapped in 6 hours, by a single person. The figure shows the dose rate map of a flooding zone of the Winterbeek, contaminated by the liquid effluents of a phosphate plant.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
An area of about 45 ha of very rough terrain, near the mouth of the Winterbeek near 0 m 500 m 1000 m 1500 m 2000 m Molenstede, contaminated by the liquid effluents of a Winterbeek phosphate plant some 15 km upstream, was measured in a foot campaign of one day and then mapped. The bread crumb trail shows the 16 km long trajectory with about 1800 data points. The radium drainage canals contamination appears to be concentrated along the main river and is also periodically 50 100 150 200 250 300 350 transported up some of the doserate nSv/h drainage canals during periods with high rainfall.
Future developments
The system will be enhanced to operate with most types of gamma detectors available at the radiation protection services of SCK•CEN For improving positional precision, the option of post processing the GPS data with readily downloadable differential GPS correction data will be investigated. A comparison of our dose rate map of the flooding zone of the Winterbeek with available aerial gamma data will be performed. The usefulness of the system as a tracer technique for identifying the frequently flooded zones of radioactively contaminated rivers such as the Winterbeek will be investigated. Precise knowledge of these flooding zones is very useful for delimiting zones in which to search for other kinds of contamination, for example heavy metals or chlorides.
Main contact person Johan Paridaens, [email protected]
Main reference J.Paridaens, "GPS-based handheld device for measuring environmental gamma radiation and mapping contaminated areas", International Congress Series, ICS 1276, Invited papers of the 6th International Conference on High Levels of Natural Radiation and Radon Areas,Osaka, Japan, 6 - 10 September 2004, in press
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INDIVIDUAL MONITORING IN MIXED NEUTRON/PHOTON FIELDS
Background Radiation protection dosimetry in mixed neutron/photon fields is still far less established than for photon radiation alone. In practice, personal dosimetry is done using passive devices with high dose threshold and not ideal energy characteristics. Also area monitor readings can deviate significantly from the radiation protection quantities. Recently some electronic dosimeters with direct reading became commercial available for neutron dosimetry. Within its 5th Framework Programme, the EC is funding the project EVIDOS which will perform an EValuation of Individual DOSimetry in mixed neutron and photon radiation fields at workplaces of the nuclear fuel cycle, with special regard to neutrons. This is a collaboration of following institutes: IRSN, PTB, NRPB, SSI, DIMNP, PSI and the SCK•CEN.
Objectives In this project workplaces in the nuclear industry in which workers can receive significant neutron doses were selected and the following tasks are carried out: • determination of the energy and angle distribution of the neutron fluence; • derivation of the values of radiation protection quantities; • determination of the readings of routine and innovative personal dosimeters and of area monitors; • comparison between dosimeter readings and radiation protection quantities. Measurements are carried out at different reactors and at fuel processing, reprocessing, transport and storage facilities (including mixed-oxides fuel facilities). These environments permit a thorough testing of the dosimeters since they differ widely in terms of dose rates, neutron/photon relative intensity, energy distributions and also temperature, pressure, humidity, acoustic noise, vibration, electromagnetic fields, etc.
Principal results We primarily performed reference field spectrometry with a Bonner-sphere system. Measurements of the double-differential (energy and direction) neutron fluence are performed with novel instruments based on superheated drop detectors and Si-diodes. Values of ambient dose equivalent and personal dose equivalent Hp(10) for the main direction of incidence are derived by multiplying the fluence distributions by the corresponding fluence-to-dose conversion coefficients. In every workplace field, all available personal neutron dosemeters are exposed. Both commercial types of active neutron dosemeters (Aloka PDM-313, Saphydose-n, EPDN2, EPDN, BD-PND, BDT) and pre-commercial types (PTB DOS2002, PSI DISN) are used. One novel reference method for Hp(10), DIMNP HpSLAB, and two novel area monitors (NRPB hybrid area monitor and the Sievert instrument) are tested as well. Also conventional area monitors for neutrons and photons as well as passive individual dosimeters (CR-39, PADC) for routine monitoring are tested.
70 300
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The MOX-rods at Belgonucléaire demonstrate the very hard energy spectrum since hardly any shielding is * present around this rack, as can be seen from these Bonner Sphere measurements. The Hp(10)/H (10) value of 0.80 shows that the directional distribution is quite uniform from the front irection. You can also see the responses of the different personal neutron dosemeters, compaired to the reference values of Hp(10) and H*(10) www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
AA first exercise was performed at the IRSN simulated workplace facility CANEL/T400 and at the thermal nneutron source SIGMA. Following this, campaign number 1 was carried out in Krümmel (Germany) inside a bboiling water reactor building and around a storage cask containing spent fuel elements. Campaign number 22 was carried out in Mol (Belgium) at the Belgonucleaire MOX fuel element manufacturing plant and at the SCK•CEN VENUS research reactor. In november 2004 measurements were done inside a pressurized water reactor building and around a transport cask in Ringhals (Sweden).
VENUS point F
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Near the VENUS reactor containment a much more isotropic neutron field is found because there is more shielding and * neutron scattering. So the Hp(10)/H (10) value of 0.25 is lower than at the MOX rack, and the neutron spectrum has a thermal peak. Again you can see the large spread in responses of the different personal neutron dosemeters, compaired * to the reference values of Hp(10) and H (10)
Experimental set-ups during the EVIDOS measurements at the VENUS reactor. On the left you can see one of the Bonner Spheres from IRSN, on the right the Sievert Instrument from SSI
Main contact person Filip Vanhavere, [email protected]
Main Reference T. Bolognese-Milsztajn, D. Bartlett, M. Boschung, M. Coeck, G. Curzio, F. d'Errico, A. Fiechtner, V. Guisti, V. Gressier, J. Kyllonen, V. Lacoste, L. Lindborg, M. Luszik-Bhadra, C. Molinos, G. Pelcot, M. Reginatto, H. Schuhmacher, R. Tanner, F. Vanhavere and D. Derdau, Individual Neutron Monitoring in Workplaces with Mixed Neutron/Photon Radiation - Radiation Protection Dosimetry (2004), Vol. 110, Nos 1-4, pp.753-758
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IMAGE QUALITY IN VASCULAR RADIOLOGY
Background In vascular radiology, the radiologists use the radiological image to diagnose or treat a specific vascular structure. From literature, we know that related doses are high and that large dose variability exists between different hospitals. The application of the optimization principle is therefore necessary and is obliged by the new legislation. So far, very little fieldwork has been performed and no practical instructions are available to do the necessary work. It's indisputable that obtaining quantitative data is of great interest for optimization purposes. In order to gain insight into these doses and the possible measures for dose reduction, we performed a comparative study in 7 hospitals.
Objectives Patient doses will be measured and calculated for specific procedures in vascular radiology and evaluated against their most influencing parameters. In view of optimization purposes, a protocol for dose audit will be set- up. From the results and conclusions in this study, experimentally based guidelines will be proposed, in order to improve clinical practice in vascular radiology.
Principal results The dose measurements confirmed that doses are high indeed and that per procedure a large variability exists between different hospitals. The skin dose measurements showed that for the interventional procedure involved, reaching the dose threshold of 2 Gy - at which skin damage occurs as a consequence of ionizing radiation - seemed very realistic. Calculated effective doses for the diagnostic procedures could also be relatively high, in the order of 10 mSv, for angiography of the lower limbs.
160 Dose-area-product (DAP) Distribution for angiography of the 140 lower limbs in the 7 contributing hospitals in the dose study
120 The quantification and analysis of patient doses in vascular radiology in 7 hospitals was very laborious, as these )
² 100 m
c procedures are complex and not very frequent. The study y.
G 80 taught us that E (effective dose) might be a useful tool for ( optimization purposes. In this point of view, new and DAP 60 appropriate conversion coefficients were determined for
40 calculation of E in vascular radiology, with the use of the Monte Carlo computer code. If every projection in the 20 examination is considered separately, E-calculations become complex and time consuming and therefore they 0 A1 B C D E F1 F2 G are only recommended for studies with a small number of patients involved.
Angiography of the carotid arteries
20 - 0 - 5 5 - 10 10 - 15 15 - 20 25 - 30 25
30 - 35 - 40 40 - 45 mGy 35
Skin dose distributions around the patient's head for angiography of the carotid arteries
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Cerebral embolisation
2 - 0 - 0,5 0,5 - 1 1 - 1,5 1,5 - 2 2,5 - 3 2,5
5 - 3 - 3,5 3,5 - 4 4 - 4,5 4,5 - 5 Gy 5,5
Skin dose distributions around the patient's head for a cerebral embolisation
However, we also established a practical calculation, where only one single conversion coefficient is used in combination with the total DAP-value (Dose-Area-Product) of the procedure.
In view of optimization purposes, dose audits have already proven their value in the past and they could also be very useful in vascular radiology, although they are not straightforward due to the complex nature of the procedures. Thorough analysis of patient doses against all procedural and technical parameters made it possible to propose a dose audit protocol and to register, next to total DAP-values, also the number of frames, the average tube voltage and possible additional copper filtration. These data can be used to determine or to compare with DRLs (Diagnostic Reference Levels) and to estimate the effective doses by means of appropriate conversion coefficients. Finally, the dose analysis also made it possible to setup some specific, experimentally based guidelines for practical dose optimization.
Future developments The research is in its final phase. A final version of the PhD will be delivered in January 2005. In collaboration with several university hospitals, we participate in a multi-centre project in Belgium that aims to optimize patient doses in vascular radiology and to evaluate their contribution to the collective dose.
Main contact person Filip Vanhavere, [email protected] Lara Struelens, [email protected], preparing a doctoral thesis based on this work.
Main reference L. Struelens et al., "Effective doses in angiography and interventional radiology: calculation of conversion factors for angiography of the lower limbs", British Journal of Radiology, 78 (2005)
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A PROTOTYPE FOR DATA AND INFORMATION EXCHANGE - MODEM
Background Following the Chernobyl nuclear disaster, a considerable amount of effort and resources have been allocated to designing and developing coherent and comprehensive decision support systems for off- site nuclear emergency management. However, events such as the criticality accident in Tokaymura in Japan, proove that there is still a lack of adequate information and data exchange mechanism that enables to share data and information, to function properly and to serve the purpose that triggered their development. It is essential for a good crisis management that dose assessments and decisions are co-ordinated and harmonised between the affected countries. Countermeasures, recommendations and information to the public and the media must be consistent. Discrepancies between assessments of different crisis centres and decision makers in different countries have to be avoided or at least be well understood. Consequently, there is a strong need for intensive, rapid and reliable exchange of all type of information. The data and information exchange prototype is part of a research project MODEM (Monitoring Data and information Exchange between Decision support Systems) that belongs to the EURATOM's 5th Framework Programme in the key action area of nuclear safety and radiation protection, carried out by a consortium of 6 European partners, under the coordination of SCK•CEN.
Objectives to achieve practical improvements in cross-boundary nuclear emergency management through the identification of the necessary data and information for decision-making; to develop and operational testing of appropriate communication procedures and techniques; thus to ensure the timely and adequate data and information flow between experts and their decision support systems in Europe.
Principal results The MODEM prototype is based on state of the art internet technology and has been tailored to operate almost automatically, thus reducing the burden on people operating decision support systems.
Schematic representation of the Decision Support System – MODEM interaction. It all begins with a notification message which has a unique ID. The processes are shown on the right hand side.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
It makes use of secure connections (ssh, https, ftps) making the exchange possible of sensitive information either through internet or dedicated lines. The prototype creates a link between the RODOS (Real time On- line DecisiOn Support system) system operated by a number of Central European countries, the ARGOS (Accident Reporting and Guiding Operational System) system, operating in Nordic and Baltic countries and RECASS (RadioECological Analysis Support System), which is used in the Russian Federation. The prototype is currently being tested and improved prior to being deployed to a number of European countries. MODEM allows the exchange of source terms, local numerical weather prediction data, results and countermeasures.
Income/Outcome messages Income/Outcome messages storage storage
Modem Web Application Modem Web Application Deployed on Apache Deployed on Apache Tomcat Web Server XML messages over HTTP/ Tomcat Web Server (Platform Independent) HTTPS (Platform Independent) Web Server Web Server
INTERNET Firewall
Firewall XML messages over HTTP/ XML messages over HTTP/ HTTPS or FTP/FTPS HTTPS or FTP/FTPS
Secured DSS network
Secured DSS network
DSS Server(s) Workstations Workstation Workstation DSS Server(s)
Exchange data between Decision Support Systems via modem software
The MODEM architecture indicating the interaction between MODEM servers receiving and storing the information
Future developments Soon data and information exchange in real time and on-line will be possible in Europe between RODOS, ARGOS and RECASS and in general any system adopting the technology and formats agreed; however, countries will have to agree to exchange information and this requires a political engagement beyond the scope of the project.
Main contact person Carlos Rojas Palma, [email protected]
Main reference Rojas Palma et al. (2004) Data And Information Exchange Prototype For Nuclear Emergency Response: Status And Future Perspectives. In: Proceedings of the Symposium on Off-site Nuclear Emergency Management, September 21-24, 2004, Rhodes, Greece.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
MULTI CRITERIA DECISION ANALYSIS ON A WASTE REPOSITORY IN MOL
Background In Belgium, the management of radioactive waste is taken care of by ONDRAF/NIRAS, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials. Local partnerships with stakeholders from municipalities in existing nuclear zones were setup to facilitate the dialogue between the repository designers and the local community. Since the establishment of the partnership in Mol, MONA (Mols Overleg.Nucleair Afval), in February 2000, all aspects of a possible near-surface or a deep geological repository are discussed in 4 working groups by around 50 volunteer members. The outcome of the discussions in the partnership can be a shared project, supported by both local stakeholders and ONDRAF/NIRAS, in which the specifications and the conditions needed for establishing a repository in Mol are elaborated. MONA asked the Decision Strategy Research Department of SCK•CEN to organise a Multi Criteria Analysis (MCA) in the context of the deciding between a surface and a deep repository for low level radioactive waste.
Objectives The objective of the multi criteria analysis is to support a number of representatives of the various working groups within MONA in their selection between two acceptable options for a repository of low level radioactive waste on the territory of Mol. The options are the surface repository developed by the working groups of MONA, and a deep repository in the clay layers underneath the nuclear site of Mol. This study should facilitate the selection between both options, or in case this appears to be difficult, at least to get a well-structured overview of all factors (criteria) of importance to the judgement, and to get insight into the degree in which the various criteria contribute to the selection.
Principal results
Criteria in bold were considered important Criteria in brown were in favor of a deep repository Workforce / accidents Criteria in green were in favor of a surface repository Workforce / occupational disease (radiological) Ground water and food chain Population / exposure to radiation Hydrologic impact Population / emergency plan Impact on land use Environment External risk: (earthquake, assaults, Other ecological impacts Safety attacks, plane crashes or climat changes) Impact of material flow Accessibility Controllability Need for controllability Retrievability
Social basis Need for retrievability Sustainability Need for a collective memory (no impact on next generations) Social Potential for learning for acceptability Mona criteria storage of high level waste Risk for abuse of installation for other Toxicity waste Health effects Impact of the worst case scenario Perception of hazards
Robustness Technical Effect inaccuracy in inventory feasibility Familiarity with technology Land use Flexibility Global costs Economical aspects Impact on image of the region Cost of a retrieval
The Multi Criteria Analysis (MCA) for deciding between the two relevant alternatives consisted of several steps: a rehearsal of the description of both alternatives at stake; the creation of a tree of criteria relevant in formulating a preference; for each criterion: determination of an evaluation scale; www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
the evaluation of the alternatives, individually and anonymously; the determination of the relative importance of the criteria, expressed both in group and individually; and a sensitivity analysis.
The alternatives were considered as input to this study, and as such were not discussed with the participants. Three meetings were organised, and several forms were created to allow a written, individual expression of opinion by all participants. About 20 volunteers from the various working groups of MONA participated to the meetings. 32 criteria were considered, grouped in 6 categories: Risk and Safety (by far the most important), environmental issues, health aspects, technical feasibility, social acceptance and economical aspects.
Indication of opposition against a repository concept Safety Social acceptability Health effects Environment Technical feasibility Economical aspects
40.0 4.2 5.7 35.0 3.2 4.3 30.0 7.2 4.0 25.0 2.1 3.4 1.9 20.0 2.5
15.0 19.0 10.0 15.5 5.0 0.0 against a surface repository against a deep repository
After evaluating both alternatives for the selected criteria, and by using the relative importance of the criteria, the main conclusions of the analysis were:
The choice between a surface repository and a deep repository is UNRESOLVED. Within the uncertainties of the method, there is NO CLEAR PREFERENCE for neither of both options. The situation shows a lot of nuance: both options are supported and harmed by several criteria. For important criteria, the mutual difference in appreciation between the options was too small to yield a clear preference in the final conclusion. The two criteria with the largest impact both orient towards a preference for a surface repository: Controllability and Retrievability. To a lesser extend: flexibility and the costs (global cost; cost of a retrieval) also point to the surface repository, but there are more criteria orienting towards a preference for a deep repository. These preferences are less pronounced than the Controllability and Retrievability mentioned above. The main ones are: (undesired) accessibility to the site (and the potential problems that could originate from this), and toxicity. Also in favour of this option, but to a lesser extend are: the necessity to maintain a collective memory, the robustness of the concept, the more limited land use in case of a deep repository and the sustainability (as part of social acceptance). We can also mention that all aspects of 'Environment' and 'Health' also point towards a deep repository A last finding worth mentioning: notwithstanding the many studies that have been performed in this context before this study was launched, it appears that many comparisons between a deep and a surface repository are based upon assessments by the participants, and hardly upon concrete numbers. As such, this evaluation reflects mainly the perceptions and opinions of the volunteers involved.
Future developments This MCA study will be part of the MONA conclusions report, which will be presented to the municipality council.
Main contact person Benny Carlé, [email protected]
Main reference B Carlé, F. Hardeman, BLG-994, "Een multi criteria analyse als ondersteuning van MONA vzw bij de keuze tussen een oppervlakteberging of een diepe berging voor laag radioactief afval in de gemeente Mol" (in Dutch), contract report CO-90 04 1176.00 MONA.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
STAKEHOLDER INVOLVEMENT FOR COUNTERMEASURES IN THE FOOD CHAIN
Background In the aftermath of a large scale radioactive contamination, the authorities will have to decide on protective measures for reducing the contamination of the food chain. The overall aim is to reduce the dose of the population to an acceptable level while still guaranteeing sufficient foodstuffs and feeding stuffs on the market and also to limit the social, environmental and economic impact of the countermeasures implemented. Many countermeasures have been developed over the years, but their large scale feasibility and especially their acceptability have hardly been studied. Within the context of a European research project called Farming (2000-2004) SCK•CEN has organised stakeholder meetings, leading to guidance to the authorities for improvements in the emergency organisation.
Objectives To improve emergency countermeasure decisions related to the food chain, especially as regards feasibility and acceptability, taking into account stakeholder opinions. The stakeholders include scientists and representatives from both governmental and non-governmental organisations.
Principal results
It was the first time in Belgium that a process of stakeholder involvement in this context was organised. The process is illustrated below. It turns out now that all stakeholders involved very much appreciate the initiative, and support the conclusions we have drawn from it.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
The main message is that almost all countermeasures after a radiological contamination show difficulties. The main operational issues are related to the very intense nature of the Belgian industry, leaving virtually no room for flexible modifications or adaptations. A second important aspect is related to the handling of the waste produced and the related environmental and legal issues. As far as acceptability is concerned, aspects of public perception and animal welfare appear to be very important. The general feeling is that the attitude of the public and the financial arrangements will be driving factors.
The work has lead to advice to the authorities in several domains: Information and communication including the differences between the information needed to decide about a countermeasure - e.g. the amount of milk produced in a zone - and the information needed to implement this countermeasure - e.g. traffic plans of the dairy industry. Preventive countermeasures to be implemented before the arrival of the radioactive cloud - e.g. closing of greenhouses. Until now, these countermeasures were not included at the European level, so our contribution was crucial here. Measurement and monitoring: our work has lead to a clearer view about the needs in the food chain, and has stimulated the creation of a working group of the Federal Agencies for Nuclear Control and for Safety of the Food chain together with the main Belgian laboratories. Aquatic pathways: it was found that mainly surface waters may cause difficulties, and that a better inventory of the water collection and emergency procedures by the tap water providers are indispensable. Belgian’s complex federal structure certainly hinders an easy approach here. Legal aspects: at many occasions, European, Belgian and Regional legislation interfere with the emergency management. The issue of reference levels seems clarified, but many legal aspects of compensation, environmental issues and animal welfare need further study.
It is worthwhile to mention that the Farming initiative has contributed to the creation of a socio-economic cell in the Crisis Centre of the Belgian authorities; this cell will be an important actor in tackling many of the advices originating from this work.
Future developments SCK•CEN and the stakeholder group are involved in the creation of a European generic manual for agricultural countermeasures. This initiative is part of the European 'EURANOS' project (FP6). The basis is the UK handbook that will be discussed with the Belgian stakeholders, and guidance will be given for customisation of intensive agricultural systems. The main conclusions of the Farming project are now available and have been sent to the main actors at the level of the authorities. SCK•CEN will continue to be active in this domain either in the implementation or as an expert or adviser.
Main contact person Benny Carlé, [email protected]
Main reference C.M. Vandecasteele, F. Hardeman, O. Pauwels, M. Bernaerts, B. Carlé, L. Sombré, "Attitude of a group of Belgian stakeholders towards proposed agricultural countermeasures after a radioactive contamination: synthesis of the discussions within the Belgian EC-FARMING group", Journal of Environmental Radioactivity, (in press).
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
COAL-FIRED POWER PLANT: AIRBORNE ROUTINE DISCHARGES
Background The radiological impact from non-nuclear industries is a growing matter of concern to stakeholders and regulators. It has been demonstrated that atmospheric discharges from coal-fired power plants can lead to higher dose-impacts to critical groups of the population than nuclear power plants. In Belgium, in the frame of an agreement between electricity producers and national authorities, measures were taken in conventional power plants to restrict airborne discharges of SO2, NOx and suspended particles. In the 500 MWe coal-fired power plant of Langerlo, a flue gas purification system was installed, consisting of a denitrification unit and a desulphurisation unit, next to the electrostatic dust filter units. These measures have also an important effect on the radioactive atmospheric discharges.
Objectives The objective of this study was to assess the radiological impact of the airborne releases of the power plant under normal working conditions and in particular the influence of the installation of the flue gas purification system.
Methods As a first step, we measured the natural radioactivity content of the coal and the radium content of the fly ash . The quantities of the other radioelements discharged through the chimney, were estimated, assuming the same behaviour as radium, except for the more volatile lead and polonium, which will condense preferably on finer ash particles, against which the electro filters are less effective. (A concentration factor of 4 has been adopted). The radon, present in the coal, is assumed to be discharged completely through the chimney. The atmospheric transport, dispersion and deposition of the discharged radionuclides were modelled, applying the bi-Gaussian plume model IFDM (by Vito). For the calculations, we used hourly averages of the meteorological observations at Mol over the year 1991. The transfers of the radionuclides from air and soil to the biospheric media, exposing man, were calculated with our biosphere model and the radiological impact to the critical group assessed. This group is considered to consist of self-sustaining farmers, having their fields in the zone of the highest annual air concentrations and depositions. The doses from the direct exposure by the plume (external irradiation and inhalation) were calculated straight-away from the maximum concentrations of 226Ra and the other radionuclides of the natural decay chains in the plume. For the doses from the deposition onto the soil, the accumulation of the radionuclides in the soil with time, has to be estimated, over the life span of the power plant (assumed to be 70 years).
Principal results
Concentration values of 226Ra in air for the measured Ra-226 discharge value of 2002 (1100 Bq/kg). When taking into account the average 226Ra concentration in the Concentration discharged fly-ash of 700 Bq/kg, the maximum annual 6. 6 nBq/m³ concentration in air becomes 4.5 nBq/m³ and the maximum annual deposition 1.5 mBq/m²y. 5 226 4 < 1 The mean concentrations of Ra and 3 232 < 2 Th measured in the coal fall within the 2 normal range (20 – 25 Bq/kg) observed < 3 1 globally for good-quality coal. The average 21 0 200 < 4 radium content of the fly-ash passing 22 0 19 0 < 5 through the electro filters was 700 Bq/kg, 23 0 18 0 <= 7 which is rather high when comparing it with 24 0 17 0 the fly-ash at other coal-firing power plants. However the total amount of 226Ra discharged and normalized to the unit power generated, was lower than that of most other installations by 1 or 2 orders of magnitude. The maximum annual value of the 226Ra concentration in the air calculated with the IFDM model is 4.5 nBq / m³ and the maximum annual value of the total deposition is 1.5 mBq / (m².y). www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 dose (Sv/year) 1,0E-07
1,0E-08
1,0E-09
1,0E-10
1,0E-11 0 10203040506070 time (year)
inhalation through submersion external irradiation through deposition inhalation through resuspension inhalation through radon exhalation ingestion food crops ingestion milk & meat TOTAL DOSE
Time-evolution of annual individual effective doses to the critical group for pathways from direct exposure to the plume and pathways from deposition on the ground. The direct external irradiation from the plume is not indicated (below scale). The flat evolution of the total dose indicates that the contribution from the direct deposition on to the food crops is much larger than the contribution from the deposition on the ground.
SUBMERSION IN THE EXPOSURE FROM DEPOSITION TOTAL PLUME
Decay External Inhalation Inhalation External Ingestion Ingestion Inhalation chain irradiation resuspension radon irradiation food crops milk&meat
U-238 3,0 E-14 3,9 E-9 4,8 E-12 4,3 E-11 2,2 E-10 3,0 E-8 5,0 E-9 3,9 E-8 chain Th-232 3,3 E-14 3,9 E-9 5,8 E-12 - 3,1 E-10 3,8 E-9 3,6 E-11 8,0 E-9 chain
TOTAL 6,2 E-14 7,9 E-9 1,1 E-11 4,3 E-11 5,3 E-10 3,4 E-8 5,0 E-9 4,7 E-8
Comparison between the annual individual effective doses from the decay chains of U-238 and Th-232, to the critical group, after 70 years of operation of the coal-fired power plant. The higher doses from the U-238 decay chain are caused by the large contributions from the ingestion of Pb-210 and especially Po-210 through the food crops.
The total annual dose after 70 years of operation of the power plant (0.05 µSv/y) is well below the exemption level of 10 µSv/y. The normalized values of the dose are up to several orders of magnitude lower than most of them in the literature. The low discharge values and the high NORM content of the fly-ash can be explained by the high efficiency of the gas purification system, reducing the quantity of fly-ash penetrating the system, but also shifting their granulometry towards lower sizes, which are enriched in NORM.
Main contact person Theo Zeevaert, [email protected]
Main reference Th. Zeevaert, L. Sweeck, H. Vanmarcke, "Radiologische impact op de bevolking na de ingebruikname van een rookgaszuiveringsinstallatie op de site Langerlo te Genk", studie uitgevoerd in opdracht van Electrabel. SCK•CEN, Mol Belgium, R-3690, 2003.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
BIOSPHERE MODELS FOR DEEP WASTE DISPOSAL
Background The management of the radioactive waste requires the implementation of disposal systems that ensure an adequate degree of isolation of the radioactivity from man and the environment. Because there are still a lot of uncertainties and a lack of consensus with respect to the importance of the exposure pathways of man, a project BioMoSA (Biosphere Models for Safety Assessment) was elaborated in the 5th Framework Programme of EURATOM). It aimed at improving the scientific basis for the application of biosphere models in the framework of long-term safety studies for radioactive waste disposal facilities. The section "radiological evaluations" of SCK•CEN took part in the BioMoSA project.
Objectives In the BioMoSA project, the reference biosphere methodology developed in the IAEA programme BIOMASS (Biosphere Modelling and Assessment methods) is implemented). We used this methodology in order to increase the transparency of biosphere modelling; to evaluate the importance of the different radionuclides and pathways, and enhance public confidence in the assessment of potential radiological dose to population groups far into the future.
Methods Five European locations, covering a wide range of environmental and agricultural conditions are described and characterised. Each participant developed a specific biosphere model for their site. In order to achieve a consistency in this model derivation, a staged approach has been followed. Successively the biosphere is described and conceptual, mathematical and numerical models are constructed. For each of the locations site- specific parameters are selected. In the project, we had the specific task to make a comparison between the model results generated by the different participants.
Principal results
Screening of the most important pathways
a I c U Pa Pu Cs R Np Cl T Pathway Se Illustration of the importance of the exposure pathway for 129 36 238 99 79 231 239 135 226 237 each radionuclide. Pathways for which the contribution to the Drinking water ingestion total dose of one of the models exceeded a certain threshold Leafy vegetable value are marked with different colours.
ingestion
Cereals ingestion Root crop ingestion Leguminosae ingestion Threshold value Pork ingestion (%) Beef ingestion ≤ 75 > 50 ≤ 75 Fruit vegetable ingestion > 30 ≤ 50 Cow's milk ingestion > 7.5 ≤ 30 Air inhalation ≤ 7.5 Fruit ingestion Soil external exposure Fish ingestion
Citrus ingestion
Soil ingestion Chicken/birds ingestion Mutton/Lamb ingestion Eggs ingestion
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
Different exposure pathways are included in the models. We observed that, for the deterministic calculations, the consumption of drinking water is the most important pathway for all radionuclides. Furthermore the contribution to the total dose from the ingestion of leafy vegetables, cereals and root crops, may not be underestimated. The ingestion of soil, mutton/lamb, chicken/birds, citrus and eggs always comprise less than 7.5% of the total dose.
U 8 400 Through irrigation, a large amount of contaminated irrigation Cl . .
) water can infiltrate into the soil. The radionuclides are taken t Cs
gh 7 350 i e I up by the roots of the plants, or migrate deeper into the soil
y_w Np layers. These processes depend on the characteristics of
dr 6 300 Pa radionuclide, soil and plant type. Here you can see the 5 Pu 250 average irrigation applied in relation to the calculated Ra 4 200 concentration in the soil for the sites. Se of food crops (l/m²/a)
in Soil (Bq/kg Tc n 3 Irrigation 150 Where a lot of irrigation is applied (e.g. Spain), the
atio concentration of radionuclides in the soil is high. Also the
tr 2 100 n influence of migration may not be neglected. So is the e
nc 1 50 irrigation in Germany higher than in Belgium, but because of Co
average irrigation higher migration rates the concentration of radionuclides in 0 0 the soil is comparable. m y n u ai ry an ga elgi rm Sp n B e Sweden G Hu
We calculated the most sensitive parameters and the variability on the end results
Monte Carlo sensitivity analysis showed that food consumption, irrigation or the distribution coefficient for soil, have the highest significant influence on the end result for almost all parent radionuclides and for most sites. Thereupon the dose distribution for most mobile elements is less scattered than the dose distribution for the sorptive elements. Mostly the ratio between the 95th and 5th percentile is never larger than 10. The high uncertainty range of some radionuclides (e.g. 36Cl,79Se) is directly coupled to the high uncertainty range of some parameters (e.g. distribution coefficient, soil-plant transfer factor).
1.E-01 . . th th
) ) 1.E-02 Comparison of the 5 and 95 % of the total annual individual dose y y Sv/ Sv/ 1.E-03 (mSv/y — normalised for 1 Bq/m³ in well water) for adults and for m m ( ( relevant radionuclides derived from the stochastic calculations at e e 1.E-04 the Belgian ( ), German ( ), Hungarian ( ), Spanish (S) and dos dos
1.E-05 Swedish ( ) site. nual nual n n a a l l 1.E-06 a a Future developments Tot Tot 1.E-07 36Cl 99Tc 129I 237Np 238U The BioMoSA project is finished, but SCK•CEN is still 1.E-08 participating in international studies for the testing and
1.E-01 verification of biosphere models, such as the new research . . programme of the IAEA, EMRAS (Environmental Modelling
) ) 1.E-02 y y / / for RAdiation Safety). There, SCK•CEN is participating in the Sv Sv 1.E-03 m m working groups dealing with the modelling of the dose ( ( e e s s 1.E-04 towards the biota, the behaviour of NORM (Naturally do do l l a a 1.E-05 Occurring Radioactive Materials) in the biosphere and the nu nu n n transport of radionuclides in freshwater rivers. a a l l 1.E-06 a a t t o o T T 1.E-07 79Se 135Cs 226Ra 231Pa 239Pu 1.E-08
Main contact person Geert Olyslaegers, [email protected]
Main reference G. Proehl, G. Olyslaegers, Th. Zeevaert, B. Kanyar, P. Pinedo, I. Simón, U. Bergstrom, B. Hallberg, S.F.Mobbs, Q. Chen, R. Kowe, (2004), "Biosphere Models for Safety Assessment of Radioactive Waste disposal" — Institut für Strahlenschutz — GSF –Bericht 06/04.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
RECYCLING OF URANIUM BY A PERENNIAL VEGETATION
Background At sites of large scale mining and processing of uranium ore, tailings and waste rock piles are today the most visible relics of the uranium extractive industry. These mining relics are constantly subjected to weathering and leaching processes causing the dissemination of radioactive and toxic elements and sometimes requiring remedial operations. The in situ remediation of waste rock piles usually includes their revegetation for minimizing the water infiltration and for increasing surface soil stability. Thanks to its biomass density and longevity, the perennial vegetation plays an important role in stabilisation of the water cycling. The buffer role of forest vegetation can reduce water export from watersheds as well as erosion and hydrological losses of chemicals including radionuclides from contaminated sites. If long term reduction of contaminant dispersion at revegetated uranium mining sites is to be fully appreciated, then the extent of radioactive contaminant availability to forest vegetation and ecosystem cycling as well as the possible economic valorisation of the woody products must be considered.
Objectives Our study focused on a Scots pine plantation established 35 years ago on a uranium waste rock pile (Wismuth GmbH) situated near Schlema (Germany). This investigation aimed at quantifying the mobility of uranium in the mining debris and its transport to the different tree compartments with emphasis on the processes involved. The influence of pine vegetation on uranium cycling dynamics was further assessed in terms of annual fluxes.
During the period from 1946 to 1990, some 220,000 tonnes of uranium were produced in the mining district of Saxony and Thuringia (Germany). Wismut GmbH is in charge of the remediation program to safely isolate and control the enormous quantity of uranium production residue. Our study was conducted in cooperation with Wismuth GmbH on dump H382 situated near Schlema in Saxony. The mining debris consisted of low grade ore dumped at that site from 1950 till 1958.
Four average Scots pine were selected in a 35-year old plantation established on the plateau of the dump H382 and aliquots of the substrate were collected from three soil profiles. Samples of major tree compartments (stemwood, stembark, branches, twigs, needles, roots) were obtained from a destructive harvest of each tree. Soil and vegetation samples were transferred at SCK•CEN for determination of uranium levels by inductively coupled plasma mass spectrometer.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
Principal results
Effect of vegetation development on uranium mobility in the mining debris With pine growth and biomass turnover, thick acid humus emerged at the surface of the substrate. Despite weathering of the alkaline mining debris, we did not observe a clear gradient with depth of the total uranium content (57-60 mg dm-3) which suggests a low vertical mobility of uranium in the profile. Increased uranium mobility mainly involved a translocation of uranium to metal-humus chelates in surface mineral layers (0-5 cm).
U in above-ground Allocation to new organs: 0.6 g U ha-1 y-1 biomass: 3.7 g ha-1
Foliage: 58 % Living branches: 12 % Internal transfer: -2.2 g U ha-1 y-1 Dead branches: 16 % Stem bark: 7 % Litterfall: 2.9 g U ha-1 y-1 Stem wood: 7 %
-1 -1 Immobilisation: 0.1 g U ha y
U in below-ground -1 biomass: 472 g ha -1 -1 -1 Uptake: 3.0 g U ha y Humus: 197 g U ha
Mining debris: 165,000 g U ha-1
The quantitative description of the processes ruling the uranium distribution and annual recycling between soil and tree compartments showed that the amount of uranium taken up and translocated from roots to upper parts represents a minor fraction of the total pool in the mining debris. Due to a prevailing uranium accumulation within the foliage, a major part of the translocated uranium can be returned to the soil through litterfall.
Description of the uranium distribution in trees and processes involved Foliage was found to be the dominant uranium sink in standing tree (58 %) whereas uranium content in wood was lowest (7 %). The prevailing accumulation of uranium in the evaporative organs made it clear that most of the translocated uranium moved passively with the transpiration stream, almost certainly in a complexed form. The total uranium incorporated in the above-ground biomass amounted to about 4 g ha-1 which is low compared to the average uranium content in the rooting zone (30 cm – 165000 g ha-1). The stump and roots accumulated, however, 100 times more uranium than the upper part.
Quantification of the uranium cycling dynamics in terms of fluxes The net root uptake of uranium amounted to about 3 g ha-1 y-1. The annual uptake exceeded by a factor 5 its allocation to new organs. That means that 80 % of the uranium transported from roots to upper portions of the tree was simply stored within older tissues, mostly senescing needles as corroborated by the high negative amount of the “internal transfer” flux for foliage. Litter fall returned to the soil 2.9 g uranium ha-1 y-1 whereas only 0.07 g uranium ha-1 y-1 i.e. ~2 % of the annual uptake was immobilized in perennial organs. By transferring to the soil 97 % of the uranium annual uptake, litter fall was shown to play a major role in tree detoxification.
Future developments The long term uranium distribution in a perennial vegetation cover will be compared with that of other radionuclides and trace elements before model development involving water and element cycling.
Main contact person Yves Thiry, [email protected]
Main reference Thiry, Y., P. Schmidt, M. Van Hees, J. Wannijn, P. Van Bree, G. Rufyikiri and H. Vandenhove. "Uranium distribution and cycling in Scots pine (Pinus sylvestris L.) growing on a revegetated uranium mining heap". Journal of Environmental Radioactivity (accepted for publication)
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
MEASURING CHROMOSOMAL ENDS OF X-IRRADIATED EMBRYOS
Background In human reproduction, the first two weeks of pregnancy cannot be detected by existing hormonal tests. Therefore, irradiation for medical purposes during this period poses a risk of damaging DNA within the cells of the newly formed embryo and could lead to malformations. p53 is a protein playing a pivotal role in DNA repair, aging and apoptosis (or programmed cell death). In our laboratory, we have previously shown the importance of this protein for normal embryonic development. Indeed, mouse foetuses deficient for the p53 protein were more prompted at developing malformations (exencephaly, gastroschisis, polydactyly, cleft palate) if they were irradiated at day 8 post conception (Baatout et al, 2002). The chromosome ends (also called telomeres) are known to be causal determinants for biological aging but are also involved in embryonic development (Bekaert et al, 2004). Since only little information is available on telomere biology early in development, we are interested in studying the telomere biology in normal and abnormal mouse foetuses within each p53 genotype (+/+, +/- and -/-).
Objectives Our ultimate goal is to find some reliable biological markers (telomeres, proteins, gene modulation, ...) that could help in understanding the molecular pathways underlying radiation-induced malformations. In this perspective, we first addressed the question of telomere length changes in the normal versus abnormal X- irradiated foetuses.
Principal results
Mouse chromosomes observed under a confocal microscope. Our goal is to find biological markers of radiation- induced malformation in the mouse foetuses. One of these markers could be "telomere shortening". Telomeres (depicted in green) are nucleoprotein structures located at the end of the chromosomes (depicted in red). The telomeric structures prevent the chromosomal ends from degradation and fusion and are essential for maintaining the integrity and the stability of eukaryotic genomes.
Cellular consequences of telomere dysfunction. The telomeric structure (t-loop) can be disrupted either indirectly by telomere shortening or directly by damage. The cells with intact p53 and RB (retinoblastoma) checkpoints respond to telomere dysfunction by undergoing senescence which may contribute to aging. If only the p53 checkpoint is intact, the cells undergo a p53-mediated cell death. If neither the p53 nor pRB pathway is intact, cells may survive with genomic rearrangements and instability, which can lead to cancer.
Cellular consequences of telomere dysfunction (Kim et al,oncogene, 2002)
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 p53 -/ - p53 +/- p53 +/+
r e
k r
a Irradiated Control Irradiated Control Control
m Malformed Malformed Normal Normal
Normal A Southern blot hybridized with telomeric N D probe. Genomic DNA was extracted from soft tissues of mouse foetuses differing in phenotype and p53 genotype. After DNA digestion and fragmentation in a field inversion gel electrophoresis, blots were analyzed via an 48.502 image analyzer and the mean telomere 38.502 restriction fragments (TRF) were determined. 29.942 19.399 12.220
Mouse females were X-irradiated at gestational day 8 of pregnancy. At day 19, the fetuses were removed by caesarean and screened under the stereomicroscope for the presence of external malformations. Highly pure DNA was extracted from the foetal soft tissues, than digested and fragmented by field inversion gel electrophoresis. After southern blotting and hybridization, blots were analyzed via an image analyzer and the mean telomere restriction fragments (TRF) were determined. No difference in the mean TRF between male and female foetuses was observed. However, when comparing the mean TRF in the foetuses with different p53 status, significantly shortened telomeres were observed within the group of double mutants for the p53 protein (p53-/-). When this latter genotype is associated to a malformed phenotype the mean TRF length is even further reduced. The foetuses showing a normal phenotype have longer telomeres than the ones harboring a malformed phenotype.
Flow-FISH technique for telomere length estimation . This method is a combination of flow cytometry and fluorescence in situ hybridization. The K-562 cell line is used as an internal control. Mouse fibroblasts
Future developments G2 The first data on telomere biology show a direct Telomere S G 1 link between telomeres and malformations. It is length K-562 cell line of importance to corroborate the results obtained G2 with TRF analysis using another well known S method: flow cytometry associated with G 1 fluorescence in situ hybridization (Flow-FISH), already optimized on cell lines (Derradji et al, 2005). Future experiments will be directed towards the investigation of telomerase activity, gene expression (using a real time quantitative PCR) and whole protein profile (using a bidimensional electrophoresis) in the normal Propidium iodide versus abnormal X-irradiated fetuses. (DNA content)
Main contact person Dr.Sarah Baatout, [email protected].
This contribution is based on the doctoral work of Hanane Derradji ([email protected]) in collaboration with the University of Gent (promoter : Prof. P. Van Oostveldt; co-promoters : Drs Sofie Bekaert and S. Baatout).
Main references 1- Baatout S, Jacquet P, Michaux A, Buset J, Vankerkom J, Derradji H, Yan J, von Suchodoletz H, de Saint- Georges L, Desaintes C, Mergeay M. Developmental abnormalities induced by X-irradiation in p53 deficient mice. In Vivo. 2002; 16(3):215-21. 2- Bekaert S, Derradji H, Baatout S. Telomere biology in mammalian germ cells and during development. Developmental Biology. 2004; 274:15-30. 3- Derradji H, Bekaert S, Van Oostveldt P, Mergeay M, Baatout S. Telomere length estimation by combination of Q-FISH and flow cytometry in human cancer cell lines. Anticancer Research. 2005, in press. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
IRRADIATION AND PAPILLOMAVIRUS E2 PROTEINS ON HELA CELLS
Background Exposure to relatively high doses ionizing radiation activates cellular responses that impair cell survival. These responses, for which the p53 protein plays a central role, form the basis for cancer radiotherapy. However, the efficacy of radiation treatments on cell killing is often reduced as a consequence of the frequent inactivation of the p53 protein in cancer cells. Loss of p53 protein is associated with later stages of most human tumors and resistance to anticancer agents. Carcinomas are frequent malignant tumors in humans. The majority of cervical carcinomas are etiologically linked to the presence of HPV virus (Human Papillomavirus). In carcinoma tumor cells, as well as in their derived-cell lines such as HeLa cells, the p53 protein is generally not detected due to its degradation by the product of the HPV-associated oncogenic E6 gene. Another characteristic of HPV-positive cervical cancer cells is the loss of the regulatory viral E2 gene expression as a consequence of viral DNA integration into the cellular genome. Reintroduction of E2 expression in HeLa cells reactivates p53, due to a negative effect on the expression of E6 protein, with a concomitant arrest of cell proliferation at the phase G1 of the cell cycle and delay in cell division via the repression of E2F-target genes.
Objectives To elucidate whether reactivation of p53 would improve the cell killing effect of ionizing radiation in cancer cells, we studied the combined effects of radiation and E2 expression on the cell cycle distribution in HeLa cells.
Principal results
E6 p53 p53 target APOPTOSIS genes HPV18 E2
ation Activ Transactivation DNA Binding G1 GROWTH domain E2 ARREST Repres E2 sion E2F target G2/M GROWTH E2-delTAD E7 pRb E2F genes ARREST TAD CELL CTRL GROWTH (a) (b)
(a) Reintroduction of E2 expression reactivates the function of p53 by negative regulation of E6. A concomitant repression of E7 protein induces cell cycle arrest either in G1 or G2 or apoptosis (programmed cell death). Blue lines indicate the cellular effects of E2. Orange lines indicate the oncogenic effect of E6 and E7 viral proteins (b) E2 recombinant forms used in this study.
E2 is a modular protein encompassing a DNA binding domain at its carboxy terminal and a transcriptional activation domain at the amino terminal. The effect of E2 was compared to two artificially truncated forms of the protein, lacking either the DNA binding domain (TAD), or the activation domain (delTAD). HeLa cells were infected with recombinant E2-expressing adenoviruses (E2, delTAD, TAD) before irradiation (X-rays). Reintroduction of E2 induced the repression of E6 transcription and concomitant reactivation of p53 protein, since the level of expression of two p53 transcriptional targets (CDKN1A and PLAB) measured by Real Time quantitative PCR was up-regulated after infection. To evaluate the cell killing effect of the combined treatment, we performed cell cycle distribution analysis by flow cytometry at regular time intervals up to 36 hours after radiation exposure. All E2 forms induced a growth arrest of the cells in a specific phase of the cell cycle. E2 induced cell cycle arrest in G1 and similar but less pronounced effect was seen with delTAD. In contrast, expression of TAD arrested the cells at the G2 phase. The combination of radiation and E2 forms expression did not greatly affect the amount of cell death at each of the tested timepoints. Although so, the strong effect on the cell cycle distribution of the all E2 forms alone, masked, only in the short term culture (36h after radiation), the combined effect with radiation. In contrast, in the long term cultures (over two weeks) a synergistic killing effect of radiation and E2 recombinants on HeLa cells was observed for one of the three forms.
www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004
E2 E6 500000 0 P53 tar get genes E2 E2-del Fold CTRL E2 E2- TAD TAD change -10 delTAD TNFRS F10 2,2 1,6 250000
GSN 2,5 3,3 -20
MVP 3 1,7 0 -30 CTRL E2 E2- TAD DDB2 3 2 delTAD
GADD45 A 3,3 1,8 RRMB2 9 3 CDKN1A PLAB CYFIP2 4 2 15 15
PA26 7 3 Fold 10 10 PLAB 9,6 2,6 change P21/CDK N1A 13 4 5 5
0 0 (c) CTRL E2 E2- TAD CTRL E2 E2- TAD delTAD delTAD (d) (c) Microarray analysis showed the up-regulation of several p53 target genes in cells where the E2 expression was reintroduced, and a less pronounced effect with E2-delTAD (d) Changes in the level of expression of E2, E6, CDKN1A and PLAB genes in all four conditions. Positive and negative values correspond respectively to up- and down-modulation of the gene.
CTRL E2 G1>G2 G1>>>G2 Cell cycle distribution was G1 analyzed by flow cytometry in G2 HeLa cells expressing the E2 recombinant forms. Comparing to a normal cell cycle distribution Number of (CTRL), E2 forms induced an cells arrest at specific phase of the cell cycle: G1 for E2 and E2-delTAD; E2-delTAD G2 for TAD. The combination of TAD radiation and E2 forms did not G1>>G2 G1 cycle distribution, only in the short term culture (36h after radiation). DNA content Future developments Based on the information obtained from E2-expressing HeLa cells, we can now investigate the combined treatment of E2 recombinant forms and radiation in other HPV-positive cells. Understanding the molecular mechanisms of radiation and E2 recombinants expression, will define novel basis for combination of radio- and gene-therapeutic treatments of cancer cells. Main contact person Benotmane Abderrafi, [email protected] Contribution is based on the work by Marcella Mori ([email protected]) in preparation of a doctoral thesis. Main references Thierry, F., Benotmane, M.A., Demeret, C., Mori, M., Teissier, S., Desaintes, C. (2004) A genomic approach reveals a novel mitotic pathway in papillomavirus carcinogenesis. Cancer Res 64, 895-903. M. Mori, M. A. Benotmane, E. L. Hooghe-Peters, F. Thierry and C. Desaintes. Combined effects of irradiation and papillomavirus E2 proteins on the cell cycle of HeLa cells. Flow and Beyond, Mol, Belgium, 23-25/9/2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 THE MOBILISATSIA EXPERIENCE Background The hazards of long-duration manned space flight are real. In order to participate effectively in long duration orbital missions or to continue the exploration of space, the health of the astronaut must be secured. There is mounting evidence that changes in the immune response of an astronaut in short-term flights, resemble those occurring after acute stress, while the changes during long-term flights resemble those caused by chronic stress. This blunting of the immune system occurs concomitant with a relative increase in microbial contamination in the space cabin environment. Such a combination of events results in an increased probability of in-flight infectious events. Micro-organisms are subject to a genetic evolution, which may lead to the capacity to colonize new environments and to cause infections. Central players in this evolutionary process are mobile genetic elements. They help to mobilize and reorganize genes, be it within a given genome (intragenomic mobility) or between bacterial cells (intercellular mobility). Hence, the processes of genetic exchange can mobilize genetic elements between bacterial strains, and therefore play a role in determining the infectious potential. The specific confined environment and space-flight related factors (such as microgravity and cosmic radiation) may increase the frequency in which mobile genetic elements are exchanged between micro organisms. Objectives The aim of the Mobilisatsia experiment was to promote microbial gene transfer under space flight conditions during a short-term experiment conducted aboard the International Space Station (ISS). The efficiency of the gene exchange process was compared with a synchronously performed ground control experiment. An experiment was carried out with well-characterized Gram-negative reference strains and one experiment was done with Gram-positive reference strains. Principal Results Study of microbial gene transfer under space flight conditions was done using the RECOMB-K: bioreactor with 3 compartments each containing a Chamber 1 culture of a test strain. At certain intervals the contents of chamber 1 and 2 were added to the chamber 3 allowing exchange of mobile genetic elements between the microorganisms. Chamber 2 Chamber 1 Chamber 3 Chamber 2 Study of microbial gene transfer under space flight conditions was done using the RECOMB-K: bioreactor with 3 compartments each containing a culture of a test strain. At certain intervals the contents of chamber 1 and Chamber 3 2 were added to the chamber 3 allowing exchange of mobile genetic elements between the microorganisms. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 During the space flight, the experiment was packed in the BIOCONT container, which was used for transportation and incubation of the RECOMB-K bioreactors. The bioreactors were packed and sent under cooled conditions to the ISS. The experimental manipulations by the responsible astronaut were limited to the mixing of the different micro organisms in the two RECOMB- K reactors. The reactors were incubated at 30 °C for a fixed period of time and afterwards stored at 4 °C until retrieval to earth. The analyses were done in laboratories at SCK•CEN and at the Catholic University of Louvain (UCL). It was observed that the exchange of genetic information between the Gram-positive bacterial strains was at least a factor 10 more efficient in the space flight experiment than in the synchronous executed ground control experiment. For the Gram-negative bacteria, no significant differences could be observed between space flight and ground control. CM140 CM1962 CM140 CM1962 RP4 pMOL222 AE815 AE815 Schematic overview of the microbial gene transfer in the Gram negative reference strains used in the Mobilisatsia experiment. The rectangles refer to the reference strains. The green and blue circles indicate the two different mobile genetic elements (RP4 and pMOL222) that can be exchanged. Upon mixing of the three microbial species, genetic material can be exchanged, each with its specific efficiency. Conclusions and perspectives The experiment indicates that micro organisms exchange genetic information under space flight conditions at least as efficient as on earth. Hence, it is envisioned that micro organisms may acquire new features under space flight conditions allowing them to colonize new environments and cause infections. This aspect is under scrutiny in follow-up projects in collaboration with the European Space Agency (ESA). Main contact person Patrick De Boever, [email protected] Main reference Patrick De Boever, Delphine Hanus, Marceline Kaufman, Michel Faelen, Jacques Mahillon and Max Mergeay. "Mobilisatsia/Plasmida space flight experiment Technical Note: 23 p". Contract PRODEX, contract nr. 90150. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 REACTOR SAFETY DIVISION Pierre D'hondt Supporting Staff Sikkie Lenaerts Instrumentation Department Scientific Staff Francis Berghmans, Benoît Brichard, Alberto Fernandez Fernandez, Ivan Genchev, Andrei Goussarov, Stan Hendrickx, Hans Ooms, Stan Van Ierschot, Marco Van Uffelen, Frans Vos. Supporting Staff Stefan Huysmans, Johny Mols, Jean Pouders, Evi Wouters. Reactor Material Research Department Scientific Staff Abderrahim Almazouzi, Rik-Wouter Bosch, Rachid Chaouadi, Willy Claes, Jozef-Pieter Cools, Anne Debremaecker, Dirk Delnooz, Flyura Djurabekova, Roberto Domingos, Ludo Eysermans, Serguei Gavrilov, Kevin Govers, August Gys, Velislava Ignatova, Maarten Jardin, Milan Konstantinovic, Ann Leenaers, Sergei Lemehov, Enrico Lucon, Lorenzo Malerba, Luc Mies, Yves Parthoens, Antonio Pellettieri, Jean-Louis Puzzolante, André Rahier, André Rempel, Leo Sannen, Danislav Sapundjiev, Johan Schuurmans, Marc Scibetta, Vitali Sobolev, Antoon Stuer, Dmitry Terentyev, Maurice Thijs, Sven Van den Berghe, Joris Van Den Bosch, Steven Van Dyck, Leo Van Houdt, Wouter Van Renterghem, Marc Vankeerberghen, Eric van Walle, Kelly Verheyen, Göran Verpoucke, Marc Verwerft, Benedictus Vos, Jozef Vreys, Jean-Pierre Wannijn. Supporting Staff Luc Bens, Rudy Bertels, Gerry Cools, Gert Cools, Marc Eykmans, Ivan Fets, François Gielens, Kris Kaers, Rik Maussen, Roger Mertens, Theo Noels, Frieda Quadflieg, Guy Rombouts, Kurt Rombouts, René Sneyers, Frans Swinnen, Nancy Van der Borgt, Herman Van Eyck, Davy Ver Heyen, Leopold Verwimp, Gunter Wilmsen, Paul Wouters. Reactor Physics & MYRRHA Department Scientific Staff Hamid Aït Abderrahim, Thierry Aoust, Baudouin Arien, Peter Baeten, Luc Borms, Simon Coenen, Chris Dams, Didier De Bruyn, Marc Dierckx, Jorg Entzinger, Wim Haeck, Simone Heusdains, Dominique Lamy, Jean-Pierre Lubamba-N'Sanda, Dirk Maes, Edouard Malambu, Nadia Messaoudi, Jozef Oeyen, Sofie Put, Da Ruan, Paul Schuurmans, Vitaly Sobolev, Leopold Truyens, Gert Van den Eynde, Chris Van Grieken, Katrien Van Tichelen, Bernard Verboomen, Jozef Verrees, Alfons Verstrepen, Ludovicus Verstrepen, Patricia Victor, Guido Vittiglio, Jan Wagemans, Victor Willekens. Supporting Staff Jan Cools, Liesbeth Dausy, Jozef Leeuws, Els Luyten, Malcolm Paget, Stefan Van Bijlen, Steffi Van Genechten, Francis Van Gestel, Ben Vanhaeren, Tony Van Nieuwenhuysen, Ivo Verwimp. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 REACTOR SAFETY: INTRODUCTION Pierre D'hondt The Reactor Safety Division focuses its programme on the development of expertise on materials behaviour under irradiation with emphasis on phenomena that occur in light water reactors. Within the Belgian context, the programme aims to guarantee safe exploitation of its nuclear power plants up to minimal 40 years of lifetime and to extend the burn-up of reactor fuel for economic reasons. Furthermore, as nuclear energy needs international public acceptance with respect to safety and efficient management of generated nuclear waste, the Reactor Safety Division enhanced its efforts on the MYRRHA project. MYRRHA, an accelerator driven sub-critical system, might have the potential to cope in Europe with the above mentioned constraints on acceptability. The Reactor Safety Division gathers three research entities: the Reactor Materials Research department (RMR), the Reactor Physics and MYRRHA department (RF&M) and the Instrumentation department (INSTR). The objectives of Reactor Materials Research are: to evaluate the integrity and behaviour of structural materials used in nuclear power industry; to perform research to unravel and understand the parameters that determine the material behaviour under or after irradiation; to contribute to the interpretation, the modelling of the materials behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the Reactor Materials Research department concentrate on four distinct disciplines: Fusion (mechanical testing and corrosion); Irradiation Assisted Stress Corrosion Cracking (IASCC); Nuclear Fuel; Reactor Pressure Vessel Steel (RPVS). The fusion research activities at RMR are an integral part of the SCK•CEN fusion research programme reported elsewhere in this report. The corrosion research programme aims to clarify the mechanisms that contribute to IASCC. Three complementary activities are developed: the modelling of IASCC and related phenomena in a computer code, that takes crucial parameters of the material, its environment and their interaction into account; experimental studies of IASCC in LWR conditions in order to generate reference data for modelling; the development of dedicated instrumentation to detect and monitor the occurrence of (IA)SCC. The fuel research activities combine both applied and fundamental research. The latter focuses on solid state research of nuclear fuel, on modelling of fuel behaviour and on the definition, technical preparation and execution of in-pile instrumented irradiation experiments. The applied research essentially remains market- driven. The tendencies of future research are the long-term intermediate storage of spent fuel and issues related to further increase discharge burn-ups. The safe operation of nuclear power plants relies primarily on the integrity of the reactor pressure vessel. Neutron exposure induces temperature dependent embrittlement of the vessel and alters the mechanical properties of the vessel materials. It is, therefore, of prime importance to monitor the material degradation by surveillance programmes. SCK•CEN is in charge of the RPVS surveillance of the Belgian nuclear power reactors and runs in parallel a research project called the Electrabel Framework agreement that supports the development of tools of use for the Belgian NPP's. Important efforts are made to integrate the discipline of material modelling into the research programmes and to support experimental projects with modelling tools. The programme on multi-scale modelling of material degradation has its applications not only for pressure vessel steel but also for candidate fusion materials. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 The objectives of the Reactor Physics & MYRRHA department are: to design, complete and analyse benchmark experiments in SCK•CEN facilities (VENUS, BR1, BR2) or elsewhere, leading to reference data for code validation in the fields of: - reactor dosimetry - core physics - reactor physics - neutron and gamma shielding - ADS systems and for specific conditions or new situations such as: - MOX fuel in LWR - transmutation of tran-uranics (TRUs) and long lived fission products (LLFPs) in burner reactors - development of MYRRHA - burn-up credit. to maintain, improve and develop experimental and computational capabilities and tools in the above fields and new areas such as: - high energy particle physics - reactor physics in sub-critical systems. To comply with these objectives RF&M in collaboration with RMR has continued the international programme REBUS (Reactivity tests for a direct evaluation of the Burn-Up credit on selected irradiated LWR fuel bundles) for the investigation of the burn-up credit. The programme aims at establishing a neutronic benchmark for reactor physics codes that calculate the burn-up credit. Maintaining high level skills in the nuclear field can only be ascertained if ambitious and innovative projects with clear objective and with realistic milestones are conducted. This is the main objective behind the MYRRHA project that in a first phase aims to design an experimental ADS followed by its construction if the technical and financial requirements are met. As such it was decided to finalize the conceptual design of MYRRHA and to focus the R&D-activities on those topics that could influence its design. These are: the hydraulic flow design of the window-less target; the vacuum interface compatibility for the window-less design; the corrosion behaviour of the structural materials in liquid metal; the structural material behaviour under irradiation; the visualisation under liquid metal; the remote-handling operation of MYRRHA. Within the 6th framework programme of the EU, the MYRRHA-team intends to play an important role in IP- EUROTRANS, an integrated project on transmutation. In all irradiation experiments, appropriate instrumentation technology is of primordial importance. The Instrumentation department evaluates the potentials of instrumentation technologies under severe constraints of nuclear applications, such as the control of nuclear power plants and the remote monitoring of waste repositories on the remote handling of hazardous materials. The Instrumentation department pays particular attention to: the application of optical fibre technology in the umbilical link of a remote handling unit for use during maintenance of a fusion reactor; the radiation hardening of plasma diagnostic systems; the study on new reactor instrumentation. Its projects cover also: space applications related to radiation-hardened glasses; developments of new approaches for dose, temperature and strain measurements; assessments of radiation-hardened sensors and motors for remote handling tasks; studies of dose measurement systems, including the use of optical fibres. Contact Pierre D'hondt, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 MYRRHA PRIMARY SYSTEM AND SPALLATION TARGET LOOP DESIGN Background MYRRHA is an ADS (Accelerator Driven System) under development at SCK•CEN. It aims to serve as a basis for the European XT-ADS (eXperimental demonstration of Transmutation in ADS). The system is to provide protons and neutrons for various R&D applications. It consists of a proton accelerator delivering a 350 MeV * 5 mA proton beam to a LBE (liquid lead bismuth eutectic) spallation target that in turn couples to a LBE cooled, subcritical fast nuclear core. The project started in 1997 and the aim is to put MYRRHA in service in 2014-2015. Objectives The objective is to fit the MYRRHA design in the prospective of the FP6 integrated project EUROTRANS. The MYRRHA team therefore finalised the pre-design phase of the spallation loop and the primary system and performed the safety assessment of the proposed design. Principal results The primary system is designed to allow extraction of the total heat produced in the vessel (60 MWth design power, including 50 MWth nominal core power) in all conditions. It should be compatible with the remote handling approach for in-service inspection & repair and for ex-vessel component manipulations and provide flexible core management for fuel assemblies and experimental irradiation devices. In 2004 the MYRRHA pre-design 3D modelling was completed. Spallation target free surface flow experiment at Kalla (FZK) Spallation loop assembly (partial vertical cut) VICE (Vacuum Interface Compatibility Experiment) www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Ex-vessel remote handling by means of telemanipulators MYRRHA design: 3D solid model (partial vertical cut) The primary system design efforts were mainly focussed on sizing the main components according to the above requirements, including thermal-mechanical stress assessments with coverage of the following components: the primary pumps and the primary heat exchangers using liquid water; the primary heat exchangers with boiling water as an alternative option, thus mitigating the consequences of water ingress in case of a heat exchanger tube rupture; an emergency cooling system and its emergency heat exchangers; the standing inner vessel with flat bottom; the diaphragm able to withstand heavy thermal-mechanical loads; the cooling system in the inter space of the outer vessel and the concrete pit shielding after omission of the water tank around the outer vessel in accordance to the recommendations made by the ITGC (International Technical Guidance Committee) in 2002. Some fundamental design options are taken for the spallation loop. The proton beam current density of 125- 175 µA/cm² necessitates a windowless target. Because of the compact design requirements of the core, a vertical confluent flow is chosen as formation mechanism for the target free surface. The spallation loop features off-axis placement of all active components away from the core for optimal access and minimal radiation damage. To accommodate this, the spallation loop is interlinked with the core by a split core support plate to allow its removal from the main vessel. The deposited thermal heat of 1.43 MWth is extracted by a by-pass flow of the LBE primary coolant. The following R&D related topics are performed: CFD calculations, water flow experiments (UCL) and LBE flow experiments (FZ Karlsruhe) to support the target nozzle design and improve understanding of free LBE surface behaviour; on-going development of a free surface level sensor (LIDAR); experiments concerning the vacuum interface compatibility, LBE conditioning and vacuum system design using the VICE set-up complemented with Monte Carlo gas flow simulations. Future developments In 2004, preparing for FP6, all European design and R&D efforts in ADS are grouped within the Integrated Project EUROTRANS. Its long term goal is to design a ETD (European Transmutation Demonstrator). The direct goal, however, is to produce the design of a first-of-a kind experimental ADS that will act as the test bench of the ETD. Within this frame and in reply to the request of the ADS and Partitioning & Transmutation community, SCK•CEN is willing to open the characteristics of MYRRHA to be updated and brought to finalization for better answering the objectives of the ETD/XT-ADS project. Main contact person Dirk Maes, [email protected] Main reference K. Van Tichelen, D. De Bruyn, D. Maes, H. Aït Abderrahim (2004) editors, Proceedings of the Topical Day "From MYRRHA towards XT-ADS A European Experimental ADS at Mol (B)", BLG – 996 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 MYRRHA PERFORMANCE AND SAFETY ANALYSIS Background MYRRHA is an ADS (Accelerator Driven System) under development at SCK•CEN. It aims to serve as a basis for the European XT-ADS (eXperimental demonstration of Transmutation in ADS). The system is to provide protons and neutrons for various R&D applications. It consists of a proton accelerator delivering a 350 MeV * 5 mA proton beam to a LBE (liquid lead bismuth eutectic) spallation target that in turn couples to a LBE cooled, subcritical fast nuclear core. The project started in 1997 and the aim is to put MYRRHA in service in 2014-2015. Objectives The sub-critical core configuration adopted for deriving the neutronics design parameters of MYRRHA ADS is displayed below. Reference MYRRHA fresh core configuration It consists of a lattice of 99 hexagonal channels of which 45 are loaded with fuel assemblies housing 30wt% Pu-enriched (Pu/HM; HM=Heavy Metal) MOX fuel pins arranged in a triangular pitch of 8.55 cm and having 3 an active length of 60 cm. The (U-Pu)O2 fuel pellets have a density of 10.55 g/cm (95%TD) and each assembly contains 91 fuel pins yielding a 514 kg load of heavy metal at beginning of life... Principal results The geometrical model for the full MYRRHA core calculation has been updated to include major components available from the engineering pre-design folder. Besides a more recent MCNPX code version offering many new capabilities and enhancements beyond former versions was used along with more appropriate nuclear data libraries. The table below gives an overview of the main parameters obtained for the beginning of life core. The MCNPX source multiplication calculation, tracking 250000 protons histories, has yielded a net production of 6.0 neutrons per incident proton (n/p). Normalised to a 5 mA-proton beam intensity, one gets an external (non-fission) source intensity of 1.88 1017 n/s. The keff-multiplication factor value, calculated by running the MCNPX calculation in the kcode-mode running 1000 cycles (100 inactive) of 40000 neutrons per cycle, is keff = 0.95521 with a standard deviation of 0.00009. The ks-value obtained from the source multiplication calculation is 0.96007 ± 0.00028. The sub-critical core delivers a thermal power of 51.75 MW (at 5 mA proton beam intensity), yielding a specific power density of 101 kW/kgHM. Beside the fission energy release, one has to take into account the power deposited by the proton beam inside the spallation target. One gets 1.43 MW. The peak linear power density for the hottest pin is 352 W/cm and the average value 272 W/cm. Aside the peak-shaped flux in the spallation region, one has at the hottest pin position beyond the spallation target flux levels reaching 1.0 1015 n/cm2s for the fast flux above 750 keV, 0.8 1015 n/cm2s for 15 2 the fast flux above 1 MeV and 4.1 10 n/cm s for the total flux. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 The accumulated DPA-damage along the T91-steel wall of spallation target peaks to 39 dpa/yr, the one- year operation cycle consisting of 3 times 90 effective-full-power-days of irradiation with 30 days shutdown period in between. The appm(He)-to-dpa ratio rises up to 8. Overview of MYRRHA ADS core characteristics (BOL) MYRRHA Neutronics Parameters Units values Proton beam energy MeV 350 Accelerator current mA 5 Proton beam heating MW 1,43 Spallation neutron yield n/p 6,03 neutron source Intensity 1017 n/s 1,88 Initial fuel mixture MOX (U-Pu)O2 Initial (HM) fuel mass (mfuel) Kg 514,1 Initial Pu-enrichment (Pu/HM) wt% 30 Keff 0,95521 Ks 0,96007 MF = 1 / ( 1 - Ks) 25,04 Source importance: φ* 1,13 ‡ Thermal Power ( ) (Pth) MW 51,75 Specific power kW/kgHM 101 Peak linear Power (hottest pin) 352 W/cm Av. Linear Power (hottest pin) 272 Max Φ in the fast core (near the hottest total 4,1 pin) Max Φ in fast core (near the hottest 15 2 >1 MeV 10 n/cm s 0,8 pin) Max Φ in fast core (near the > 0 .75 MeV 1,03 hottest pin) A typical core loading pattern was adopted to assess the potential of MYRRHA as to the transmutation of U-free MA consisting of (Pu0.4-Am0.5-Cm0.1)O2-x mixed oxide fuel smeared in an MgO inert matrix. Calculations have yielded an incinerated amount of MA is 876 g over an initial load of 18.09 kg. A safety analysis of MYRRHA has been performed with the RELAP and SITHER codes. The most limiting transients were considered. It was demonstrated that, thanks to the intrinsic safety features of the machine and a total passive decay heat removal system, none of the protected transients (proton beam off) poses a serious problem. Some unprotected transients (proton beam on) on the other hand show unacceptable consequences highlighting the necessity of a highly reliable beam trip system. In addition a Computational Fluid Dynamics model with the FLOW-3D code has confirmed the capability of MYRRHA to be cooled by natural circulation in emergency situation Future developments Further studies are under way to obtain reliable core kinetic parameters and to carry out various sensitivity studies. Main contact person Edouard Malambu, [email protected] Main reference E. Malambu, Th. Aoust, W. Haeck, N. Messaoudi and G. Van den Eynde, “Sub-critical Core Neutronics Design Calculations” in MYRRHA ADS Pre-Design folder, Draft.2. In preparation www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 VENUS International Programme: REBUS Background Present criticality safety calculations of irradiated fuel often have to model the fuel as fresh fuel, since no precise experimental confirmation of the decrease of reactivity due to accumulated burn-up exists. The disregarding of this so called burn-up credit limits the stacking density of spent fuel and hence has serious economical implications for transport, storage and reprocessing of irradiated fuel. For long-term geological storage it is almost imperative to apply burn-up credit. Objectives The aim of the REBUS-PWR programme is to establish an experimental benchmark data base for the validation of reactor physics codes for the calculation of the loss of reactivity due to burn-up for PWR fuel, both for UO2 and MOX fuel bundles. The programme consists of the loading of five different configurations at the VENUS critical facility: an entire fresh UO2 reference configuration, a fresh and a spent UO2 fuel configuration and, a fresh and a spent MOX fuel configuration. The spent UO2 fuel coming from the German Neckarwestheim NPP has a burn-up of 51 GWd/tM, whereas the spent BR3 MOX fuel has a burn-up of 20 GWd/tM. For all these configurations, the critical water level and reactivity effect are determined. Fission-rate and flux distributions are measured in the different configurations except for the reference configuration. To allow a thorough validation of reactor physics codes, the fresh and spent fuel are well-characterised by non-destructive ( -spectrometric) and destructive (radio-chemical analytical) techniques. Principal results The REBUS rodlet design comprises a precisely dimensioned fuel stack c within a well defined overall design (end plugs d and extension pieces efg). The metallographic examination of the circular end plug weld shows that the applied orbital TIG welding method produces a perfect bonding between the cladding and the end plug. Prior cladding – end plug interface www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 The seal weld process provides a closure of the end plug central gas filling/venting hole with a Zry wall thickness equivalent to the end plug side wall thickness. . View of the REBUS bundle structure Positioning of the REBUS container on the supporting One of the major achievements in the REBUS project in 2004 was the refabrication of 26 short (~ 1 m) fuel rodlets from 13 long (~ 4 m) industrial irradiated UO2 fuel rods with a burn-up of 51 GWd/t and a cooling time of about 7 years. The refabrication process applied allowed to refabricate all 26 rodlets in full compliance with the specifications given by the experimentator and the fuel owner. The end plug weldings were thoroughly qualified, such that a proper (i.e. tight, defect free and corrosion resistant) closure is assured for each rodlet. This also allows to reconstitute original full-size rods for re-insertion in the original fuel assembly at the program end. Finally the rodlets -being seriously contaminated by the refabrication process- were cleaned with the in-house developed MEDOC process that is based on chemical decontamination with a ceriumsulfate solution down to very low residual contamination levels (< 3 kBq/dm² β,γ and < 0,3 Bq/dm²α ). The clean refabricated rodlets were then assembled in a REBUS bundle and transported to the VENUS critical facility. After a successful remote loading of the bundle in the VENUS reactor, the associated experimental programme was completely carried out. From these measurements, the reactivity difference between a fresh UO2 bundle and an irradiated UO2 bundle with a burn-up of 51 GWd/t was determined. The program includes a full relevant characterisation of the irradiated fuel by the radiochemical assay of both fuel types (MOX fuel and UO2 fuel). These analyses were partly finished in 2004 and will be completed in the beginning of 2005. Future developments An extension of the current REBUS-PWR project with a BWR phase has been signed. This BWR phase will contain a configuration with 16 1 m refabricated irradiated BWR-rods with a burn-up ranging between 40 GWd/tM and 70 GWd/tM. The refabrication and characterisation will be finalized in the first halve of 2005. The experimental programme in the VENUS reactor is foreseen for the middle of 2005. Main contact person Peter Baeten, [email protected] Main reference P. Baeten, P. D'hondt, L. Sannen, D. Marloye (BN), B. Lance (BN), A. Renard (BN), J. Basselier (BN), "The REBUS Experimental Programme for Burn-up Credit", ICONE12 International Conference on Nuclear Engineering, Arlington, Virginia (Washington D.C.), USA, April 25-29, 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 VALMOX: VALIDATION OF NUCLEAR DATA FOR HIGH BURN-UP MOX FUELS Background VALMOX is one of the projects of the cluster EVOL (Evolutionary Fuel Concepts: High Burn-up and MOX Fuels), which is part of the research programme on Nuclear Energy, Safety of the Existing Installations. Four companies are engaged in this work: BN (Brussels-B), SCK•CEN (Mol-B), CEA (Cadarache-F) and NRG (Petten-NL). Objectives Entirely devoted to MOX assemblies in Light Water Reactors, VALMOX comprises the evaluation of the actinide and fission product inventory of MOX fuel at high burn-up (typically 60 GWd/t), with special attention to the helium production. Calculated values for the spent fuel isotopic masses are to be compared to the measured ones, with sensitivity analyses made in support. JEF-2.2 nuclear data is taken as a basis for the calculations. The resulting recommendations on nuclear data should be employed in the preparation and testing of the next JEFF-3.1 file. The VALMOX work is based on the best available analyses of spent, commercial MOX fuel, for burn-up of 60 GWd/t and higher. It includes MOX irradiations data from Saint- Laurent-des-Eaux and Dampierre (CEA) and data from the ARIANE programme (BN and SCK•CEN). SCK•CEN is responsible for the MC calculation of the ARIANE irradiation experiments which took place from 1990 to 1996 in the 400-MWe PWR of Beznau-1. Principal results Comparison between ALEPH and APOLLO-2 for the OECD Comparison of ALEPH (JEF-2.2 and JEFF-3.0) and WIMS-8a BUC Phase VI-B benchmark after 1320 days of irradiation (48 (JEF-2.2) relative deviations against experimental values for GWd/t). the ARIANE Beznau-1 BM1 sample (1720 days - 46 GWd/t). www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Neutron energy spectrum for the BUC single pin model at ALEPH multi-assembly model for the Beznau-1 reactor. The begin of life and end of life (1320 days - 48 GWd/t). One sees model consists of UO2 pins (yellow), H-MOX (orange), M- clearly the self-shielding effects of the Pu 239 (n,γ) resonance MOX (green), L-MOX (red), guide and instrumentation tubes at 0.3 eV and the Pu240 (n,γ) resonance at 1.06 eV. (blue). Each fuel pin is followed separately. The application of the MC method to the field of burn-up calculations leads to powerful tools with a broad area of applications. These tools are however quite demanding on calculation time. To try and solve this problem, we developed ALEPH, a very efficient MC burn-up code using any version of MCNP(X) for spectral calculations, a slightly modified version of ORIGEN-2.2 for evolution calculations and NJOY-99.90 for nuclear data processing. ALEPH uses a multi-group approximation to the MC tallying procedure which is computationally faster. By allowing a small tolerance for the reaction rates evaluation, say 1-σ relative difference between MCNP(X) and ALEPH, we reduced the total calculation time by a factor 30. A typical multi-assembly calculation for Beznau-1 requires 4 hours of CPU time (40 CPU parallel calculation). The equivalent cell calculation takes only 5 minutes (3 hours on a PC). ALEPH was first compared against WIMS-8a (BN) and APOLLO-2 (CEA) for the OECD BUC Benchmark (see the figures above). The agreement is excellent except for Np237. For the ARIANE samples, ALEPH gives generally better results than WIMS-8a (BN). Recalculation with JEFF-3.0 cross sections reflects the improvements due to the changes introduced in the basic data. Future developments Time step optimization, direct fission yields treatment, incorporation of JEFF-3.0A activation files Main contact person Bernard Verboomen, [email protected] Contribution is based on the work by Wim Haeck ([email protected]) in preparation of a doctoral thesis. Main reference B. Lance, S. Pilate, R. Jacqmain, A. Santamarina, D. Bernard, B. Verboomen, J.C. Kuijper. VALMOX: validation of nuclear data for high burn-up MOX fuels. Nuclear Engineering and Design, (2004) (article in press). S. Pilate et al. VALMOX: validation of nuclear data for high burn-up MOX fuels-final report. Contract n°FIKS- CT-00191 (2005). W. Haeck, B. Verboomen, H. Aït Abderrahim, C. Wagemans. ALEPH: an efficient approach to Monte Carlo burn-up. The Monte Carlo Method: Versatility Unbounded in a Dynamic Computing World. Chattanooga, Tennessee, April 17-21, 2005, American Nuclear Society, LaGrange Park IL (2005). www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 PERFECT: STRESS CORROSION CRACKING IN REACTOR CORE INTERNALS Background PERFECT is a European Community sponsored integrated project. The project is to develop multi-scale numerical tools capable of simulating the effects of irradiation on mechanical and corrosion properties of materials. SCK•CEN is playing a major role in the project and manages the "Internals - Mechanics & corrosion" sub-project in which it collaborates majorly with CEA, SERCO, CIEMAT, FANP, VTT and VUB. This sub-project focuses on the description of the behaviour of reactor internals under irradiation and in contact with the reactor environment. Under these conditions, Irradiation Assisted Stress Corrosion Cracking (IASCC) can become a life-time limiting factor for the component. Objectives The objective of the work is to create and verify a predictive code for the behaviour of reactor internals, subject to IASCC. As the life-time of a component, consists of an initiation and propagation period, the IASCC module will be built around a crack initiation and a crack growth module. These modules will be supported by two modules, describing the local environmental (electrochemical) conditions in cracks and crevices and the macroscopic mechanical behaviour of cracked components. The approach to the crack initiation model will be twofold, addressing both the statistical nature of the process and the physical basis of passivity breakdown of the material. The statistical approach will be supported by systematic testing of cold worked and proton irradiated (as the initiation phenomenon is surface dominated) specimens, yielding a Weibull type of relationship between initiation and stress, environment and surface condition. The physical - deterministic - studies will be based on a point defect type of model, describing the interaction between environment and material through the passive film, formed on it. The crack propagation should be modelled by a multi-scale approach, taking into account the following aspects: Microscopic crack propagation: modelling of the interaction between corrosion induced point defects, dislocations at the crack tip and radiation damage in the grain matrix. This model will link to the physics sub project by the discrete dislocation dynamics modelling of irradiated stainless steels. Mesoscopic crack growth: the propagation of a crack in a multi-grain array is modelled based on the microscopic model predictions and the stress distribution between grains. This stage will link the microscopic model to the mechanical behaviour model, which considers the material as a continuum. Macroscopic crack growth model: crack propagation is modelled on a macroscopic scale, based on the distribution of stresses, strains and strain rates around the crack tip and the electrochemical conditions around the cracked body and at the crack tip. The constitutive laws for crack propagation will be determined based on the microscopic and mesoscopic modelling, for which the macroscopic model is defining the electrochemical and mechanical boundary conditions. Principal results 5 4 s m/ 0 3 -1 0 15 1 R, 2 20 CP MPa√m 25 1 29 33 0 0 200 400 600 [O2], ppb The influence of the dissolved oxygen concentration on the crack propagation rate of stainless steel in a dilute sulphuric acid (0.27 µS/cm) solution at 288°C for various values of the stress intensity. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 5 ppbO2 s 4 100 m/ 0 150 -1 3 0 200 1 2 300 R, 500 CP 1 0 0 10203040 K, MPa√m The influence of the stress intensity on the crack propagation rate of stainless steel in a dilute sulphuric acid (0.27 µS/cm) solution at 288°C for various values of the dissolved oxygen SCK•CEN's achievement for 2004 is the development of an indicative numerical simulation tool, the "SS/H2SO4 demonstrator", for crack propagation in stainless steel in a diluted sulphuric acid solution. The SS/H2SO4 system's conductivity is representative for the high-temperature high-pressure water environment in a BWR. The crack propagation rate results have been obtained by assuming that the slip-dissolution mechanisms is operative and by simultaneously solving the mass transport equations for all species in the crack internal and external environment using finite elements. The SS/H2SO4 demonstrator allows to picture the influence of dissolved oxygen concentration, sulphur content, temperature, stress intensity, crack length, fluid flow, sensitization and yield strength on the crack growth rate. The SS/H2SO4 demonstrator was developed in collaboration with the Vrije Universiteit Brussel and has been distributed amongst the partners of PERFECT for evaluation. Future developments The next step is to develop, along the same lines, a macroscopic crack growth model for stainless steel in boric acid – lithium hydroxide solutions. Main contact person Steven Van Dyck, [email protected] Main reference www.fp6perfect.net www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 OMICO: MICROSTRUCTURE OF OXIDE FUELS Background After typically three to five years in a power reactor of the type used in Belgium (Pressurised Water Reactor, PWR) nuclear fuel has reached its "burn-up" limit and is discharged. At discharge, only a small fraction (5%) of the heavy atoms is fissioned. Unlimited increase of this percentage is not possible with the current generation of reactors, but technological improvements are expected to add another five percent of total fissioned atoms at discharge, which means doubling the efficiency of nuclear fuel! Objectives Limiting to such efficiency increase is the behaviour of gaseous fission products: xenon and krypton. These tend to form bubbles in the fuel (see below), to escape to the free volume of the fuel rod and hence to increase the fuel rod inner pressure. Cross-section of a nuclear fuel rod after irradiation. (a) Entire cross section (size bar = 1 mm). (b) and (c) At high magnification, one observes small bubbles filled with fission gas created during irradiation. The growth and movement of such bubbles and the way they release their gas is the subject of the project OMICO. When its design limit is reached, a rod is discharged from the reactor even when its fission potential is not yet fully exhausted. Therefore, one tries to develop fuels with better gas retention and to increase the knowledge of the release mechanisms. A better understanding of the phenomena governing these release mechanisms is underlying to further developments in predictive and safety oriented modelling of nuclear fuels. The OMICO project studies three different fuel compositions (UO2, (U,Pu)O2 and (Th,Pu)O2), and for each type, two different microstructures are compared (homogeneous and heterogeneous). Fuel was produced at the Institute for Transuranium Elements (ITU) and the rods are irradiated in the CALLISTO loop of the SCK•CEN's BR2 Materials Test Reactor in which the conditions of a real PWR are reproduced. The six different fuels are irradiated in segment pairs, one segment being instrumented with a central thermocouple and a gas pressure transducer. In this way, the temperature and pressure inside a fuel rod can be studied during the irradiation. The second, non-instrumented set will be unloaded at regular intervals in order to perform non-destructive investigations. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Principal results Temperature Profiles during Start-up (cycle 2004/5) 1200 600 TC_UO2 °C TC_(U,Pu)O2 °C B 1000 TC_(Th,Pu)O2 °C 500 Power_UO2 Power_(U,Pu)O2 800 Power_(Th,Pu)O2 400 C) (° e r wer (W/cm) tu A o P era r a 600 300 e Temp d e Lin e r ag u r s Mea 400 200 Rod Ave 200 100 0 0 8:00 10:00 12:00 14:00 16:00 18:00 20:00 22:00 Time Measured centreline temperatures for three rods of the OMICO at first start-up. Due to different positions in the reactor, the rods have slightly different powers. At all times, the power of the (Th,Pu)O2 rod is higher than the other two. Yet, this rod has the highest centerline temperature only during the early phase of start-up (zone A), when the thermal barrier of the gap between the fuel and its cladding is most important. At higher power levels, the superior thermal conductivity of (Th,Pu)O2 as compared to either UO2 or (U,Pu)O2 results in lower centreline temperatures even at higher power levels (zone B) The OMICO project is loaded in the CALLISTO loop of the BR2 reactor and went to power in cycle 2004/5 (see graphic above). In this loop, the thermo-hydraulic conditions of a real PWR are simulated. For the OMICO experiment which contains a set of instrumented fuel rods equipped with centreline thermocouple and gas pressure transducers, a new feed-through system for 40 instrumentation cables was designed and developed. This feed-through system proved to be successful and is now copied to the other two in-pile sections of the CALLISTO loop: instrumented irradiations in PWR conditions can now be fully exploited! ITU performed the manufacturing of the fuel where it contributed to the development of advanced MOX fuels, both in the MIcronised MASter (MIMAS) production route and the sol gel route. The in-pile performance assessment of these fuels starts now and together with the production experience, might lead to novel fuels with improved fission gas retention. ITU performed also the fuel rod assembly was, and the qualification of the rod welding was performed by SCK•CEN. The experience gained in this process was essential for the hot-cell fabrication of 26 short fuel rodlets from pre-irradiated, industrial size rods for the REBUS program. Future developments The OMICO project combines theoretical and experimental nuclear expertise from several organisations. Apart from direct objectives of these projects, namely the study of the influence of microstructure and matrix on fission gas release, advances will be made in fuel fabrication technology; in-reactor experimenting and complex modelling. The study of fundamental properties of nuclear fuel, the physics of ultra-high burnup fuels, MOX fuels from multiple recycling strategies, etc. are logical continuations of OMICO and are topics proposed in an Expression of Interest for the 6th FP proposal LWRTRANS and integrate in the 6th FP Integrated Project EUROTRANS Main contact person Marc Verwerft, [email protected] Main reference Further information can be found on our OMICO website www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 IRRADIATED STEELS IN PB-BI EUTECTICUM Background At present the interests to liquid metals (LM) arise from research activities towards Accelerator Driven Systems (ADS) MYRRHA, new generation fast breeder reactors and fusion reactor development. In general liquid metals are selected because of their good nuclear, heat conducting, and thermal-hydraulic properties. For MYRRHA lead bismuth eutectic (LBE) is selected as coolant and spallation neutron source. However, besides the advantages LBE offers for MYRRHA ADS concept, the corrosion issues may cause difficulties in its use. Two phenomena are of practical interest: general corrosion including uniform penetration and dissolution, preferential dissolution of alloying elements, and localised attack consisting of inter granular penetration and when stress is present liquid metal embrittlement (LME). Objectives Our main objectives are to evaluate and study the general and localised liquid metal corrosion aspects on two primary selected materials for ADS MYRRHA (namely T91 and A316L) and other materials for advanced nuclear applications as EM10, HT9, F82H, EUROFER97, and ODS EUROFER97. In addition we are investigating the synergetic effects of liquid lead bismuth eutectic and neutron irradiation on the mechanical properties of these materials. Principal results Stable oxide, transition, and dissolution corrosion modes on T91 materials exposed to liquid LBE at temperatures >500ºC. Fracture surface of neutron irradiated A316L and T91 steels tested in liquid LBE. A316L T91 Unirradiated, Pb-Bi Unirradiated, Pb-Bi 800 800 Irradiated 1.46 dpa air Irradiated 1.15 dpa, ai 700 Irradiated 1.46 dpa, Pb-Bi 700 Irradiated 1.15 dpa Pb a a P 600 Irradiated 1.58 dpa Pb P M Irradiated 1.72 dpa, Pb-Bi 600 Irradiated 1.70 dpa Pb 500 ess, 500 str 400 g n 400 i r 300 ing stress, M 300 ginee 200 En 200 100 Engineer 100 0 0 0.05 0.1 0.15 0.2 0.25 0 Engineering strain 0 0.05 0.1 0.15 0.2 0.25 Engineering strain Tensile curves of neutron irradiated and unirradiated A316L and T91 tested in LBE. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Comparison between three ferritic martensitic T9 steels tested in liquid LBE before and after neutron Unirradiated, Pb-Bi irradiation to 2.5 and 4.36 dpa. 800 1 Irradiated 1.15 dpa, air 700 Irradiated 1.15 dpa Pb-Bi Engineer ing stress, MPa Studying the general corrosion effects on Irradiated 1.58 dpa Pb-Bi 600 Irradiated 1.70 dpa Pb-Bi A316L and T91 materials under poor oxygen 500 conditions in the temperature region 400- 400 600°C we found temperature and time 300 dependent corrosion process. Above 500°C we found three distinguishable corrosion 200 modes: stable oxide film mode, transition 100 corrosion mode, and final dissolution 0 corrosion mode. On the next page, typical 0 0.05 0.1 0.15 0.2 0.25 Engineering strain micrographs on the cross section of T91 materials from these corrosion modes are shown. At these temperatures, T91 material EM10 had a better corrosion resistance than A316L Unirradiated due to long lasting oxide formations on its 800 Irradiated 2.93 dpa, air surface. Below 500°C, both materials were 700 Irradiated 4.36 dpa, air mildly attacked but A316L has better a Irradiated 2.93 dpa, Pb-Bi P 600 corrosion resistance. M Irradiated 4.36 dpa, Pb-Bi , s 500 We investigated the effect of LBE on the mechanical properties by slow strain rate 400 ng stres (SSR) tests at 200 and 250°C. These tests 300 neeri aimed to investigate whether these materials gi 200 En are prone to LME and to serve as a base for 100 comparison of the effect of neutron irradiation 0 and liquid LBE. For this sake, we built liquid 0 0.05 0.1 0.15 0.2 0.25 metal embrittlement test station 1 (LIMETS1) Engineering strain allowing tests in LBE and control and variation of the dissolved oxygen HT9 concentration. We did not find any of the materials to be susceptible to LME by LBE at Unirradiated air 200 and 250°C. However, the resulting post 1000 Irradiated 2.55 dpa, air irradiation embrittlement and hardening could a Irradiated 4.33 dpa, air P 800 Irradiated 2.55 dpa, Pb-Bi affect the sensitivity to LME as harder M , s Irradiated 4.36 dpa, Pb-Bi materials are generally more susceptible to res t 600 LME. This expectation was not confirmed ng s during the post irradiation SSR tests in liquid 400 eeri n i lead bismuth eutectic after neutron irradiation Eng 200 up to 4.36 dpa. 0 0 0.05 0.1 0.15 0.2 0.25 Engineering strain Future developments We are executing a profound test matrix to validate the selection of A316L and T91 as structural materials. In parallel, we are investigating the effect of temperature, oxygen concentration, chromium content, strain rate, and other parameters which may influence the susceptibility of LME. Irradiation experiment of materials in liquid lead bismuth eutectic is under preparation. We are building second experimental set-up LIMETS2 designed for mechanical tests on irradiated materials. It will be installed in a hot-cell of our laboratory LHMA and will allow testing in liquid lead lithium and lead bismuth eutectics. Main contact person Danislav Sapundjiev [email protected] Main references D. Sapundjiev, “Static exposure tests in liquid Pb-Bi eutectic”, SCK-CEN, BLG-970 (2004). www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 IN-CASCADE CLUSTERING IN FE-CR ALLOYS Background Irradiation experiments on Fe-Cr alloys show that adding Cr up to a concentration of 12wt % leads to a pronounced decrease in swelling compared to pure α-Fe, as well as to austenitic steels, with a complicated dependence on Cr concentration and irradiation temperature. Experiments also show that the addition of even small percentages (0.1at%) of Cr to ultra-pure Fe induces more frequent nucleation of small interstitial loops than in ultra-pure Fe and that interstitial loop motion in Fe is significantly slowed down by the presence of Cr. Interstitial loop in-cascade production and mobility are known to be important parameter in determining the development of swelling. Objectives Molecular dynamics (MD) is a widely used tool for the study of atomic-level processes and is particularly well-suited for the simulation of displacement cascades and the analysis of the mechanisms of formation and motion of interstitial atoms and their clusters, provided that a suitable inter atomic potential is available. In this work we used an Embedded Atom Method potential developed to describe Fe-Cr alloys in the range of concentration around 10at%Cr to study in-cascade interstitial cluster formation in Fe and Fe-10at%Cr alloys. The attention was focussed on the analysis of the interstitial population at the end of the cascade, from the standpoint of clustered fraction and chemical nature of the interstitial atoms. Numerical distribution of clustered defects, size of clusters and mechanisms of their formation were studied as well. Principal results For pure Fe the results obtained are comparable with previous work, provided that similar criteria for cluster analysis are used. The possible mechanisms involved in interstitial cluster formation, both in Fe and in the alloy, have been briefly discussed and a correlation between sub cascade splitting and larger interstitial clustered fractions has been observed. Two are the net effects of the presence of a high concentration of solute atoms strongly interacting with interstitials in Fe, as Cr atoms may be. On the one side, most isolated interstitials are solute atoms, in a proportion far above the average solute concentration in the alloy. These appear to be less mobile than self- interstitial atoms and hence less likely to produce further cluster growth. Nonetheless, interstitial clusters containing a fraction of solute interstitial atoms always larger than the average solute concentration in the alloy are produced and this Cr aggregation inside clusters may be a thermal spike effect. The total number of interstitial atoms produced in the cascade and even the in-cascade interstitial clustered fraction, however, do not appear to be significantly influenced by the presence of solute atoms in high concentration. If the mixed interstitial clusters produced in the cascade turned out to be significantly more stable and less mobile than interstitial clusters in pure Fe, then a key for the understanding of the effects of Cr on the micro structural evolution of ferritic alloys under irradiation may be provided. 0.8 0.7 on i act 0.6 fr d re 0.5 e ust 0.4 cl al Fe-10% Cr this work ti 0.3 Fe this work rsti e t Fe-FS-100K n 0.2 I Fe-FS-600K 0.1 0 1020304050 Energy, keV Interstitial clustered fractions versus in-cascade energy. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 (a) (b) 200 nm 200 nm 200 nm 200 nm Correlation of sub cascade splitting and enhanced clustered fraction. (a) (left) 40-keV dense cascade (above), with final small fraction of interstitials in clusters (below); (b) (right) 40-keV split cascade (above), with final formation of large interstitial clusters (below). Future developments The results obtained are supposed to be used as input data for kinetic Monte Carlo codes, which enable the behaviour of these defects to be studied in a perspective of long-term evolution. Main contact person Dmitry Terentyev, [email protected] Main reference D. A. Terentyev, L. Malerba M. Ho, "In-cascade interstitial cluster formation in concentrated ferritic alloys with strong solute-interstitial interaction: a molecular dynamics study", u, accepted for publication in Nuclear Instruments and Methods in Physics Research B. This contribution is based on the work of Dmitry Terentyev in preparation of a doctoral thesis. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 FUSION CERAMIC MATERIALS AND COMPONENTS Background Present-day approach for the radiation hardness assurance of components and materials for the International Thermonuclear Experimental Reactor (ITER) is based on extensive testing under representative conditions. Those conditions include radiation, temperature and vacuum and the possibility of in-situ monitoring of radiation-induced changes in characteristics of interest. The resistive bolometers are an example of an ITER component currently tested at SCK·CEN. Bolometers will be used for the plasma emission monitoring in high-radiation and high-temperature locations such as the divertor region. Previous tests with bolometers having gold strips on mica substrates were performed in the JMTR (Japan) and revealed problems of adhesion of the strips on the mica surface, which naturally has a very low roughness. A new type of the resistive bolometer based on platinum meander on alumina or aluminum-nitride (AlN) substrates have to be tested at a high neutron flux (0.01 dpa), high temperature (400 C) and in vacuum (~10-3 mBar)- conditions appropriate for the ITER. Another illustration of on-going radiation testing for the ITER is the investigation of the Radiation-Induced Electrical Degradation (RIED). RIED is degradation of electrical insulation under the combined effect of radiation, temperature, vacuum and a strong electric field. It may be an issue to be dealt with in the design phase. Objectives Our objective is to develop instrumentation capabilities, which can provide in-situ data on the radiation hardness of materials and components intended for the use in the ITER. These capabilities will allow assessment of the performance parameters under conditions representative in terms of radiation load, temperature and vacuum, and will include on-line electric measurements. Principal results Pt meander Bolometer substrate (AlN) www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 A vacuum capsule with a bolometer holder was designed and fabricated in order to allow in-reactor meander resistance and substrate insulation measurements. This capsule has no active heater while temperature ~400 °C relevant for the ITER is provided via gamma-radiation heating. The geometry of the bolometer holder was defined based on numerical simulations. The complexity of the design was related to the condition that the outer surface of the capsule is in contact with water in the irradiation channel and the water temperature is about 60 °C. To study the RIED, we built a versatile rabbit-type irradiation rig, in which the insulation of ceramic samples may be studied under active vacuum and electrical bias at temperature up to 350 °C. Future developments Continue testing of bolometers with new designs and substrate materials, including capacitance-type bolometers with ferro-electric substrates. A special cycle of BR2 is scheduled in 2005 for the RIED test. Main contact persons Andrei Goussarov, [email protected] Hans Ooms, [email protected] Main reference A. Gusarov , L. Vermeeren, B. Brichard, R. van Nieuwenhove , A. Fernandez Fernandez, H. Ooms, M. Decréton and F. Berghmans, "In-situ in-reactor testing of fusion materials and components", presented at 23rd Symposium on Fusion Technology, 20 - 24 September 2004 - Fondazione Cini, Venice, Italy. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 COMMUNICATION LINKS FOR FUSION REACTOR MAINTENANCE OPERATIONS Background Different architectures are envisaged for data transmission with fibre optic links in a radiation environment, as proposed in literature for both space and high energy physics applications. Their needs and constraints differ from those encountered for maintenance tasks in the future ITER environment, not only in terms of temperature and radiation levels, but also with respect to transmission speed requirements. Our approach attempts to limit the use of radiation-sensitive electronics for transmission of both digital and/or analogue data to the control room, using glass fibres as transport medium. We therefore assessed the radiation behaviour of a cost-effective fibre optic transmitter at 850 nm, consisting of a PWM (pulse width modulator), a radiation tolerant current driver (previously developed at SCK•CEN) and a VCSEL (Vertical-Cavity Surface Emitting Laser assembly, up to 10 MGy at 60 °C. The PWM enables us to transform an analogue sensor signal into a pseudo numerical signal, with a pulse width proportional to the incoming signal. Objectives The main objective of this task is to contribute to the major design of the maintenance equipment and strategy needed for the remote replacement of the divertor system in the future ITER fusion reactor, with particular attention to the implications of radiation hardening rules and recommendations. Next to the radiation assessment studies of remote handling tools, including actuators and sensors, we also develop radiation tolerant communication links with multiplexing capabilities. Principal results Ouput PWM 2 @ 5 kHz 100 recovery a 90 5.0 V 80 4.8 V 4.6 V 70 4.4 V 60 4.2 V [%] e 3.8 V cl y 50 4.0 V c y 3.6 V 40 Dut 3.4 V 30 3.2 V 3.0 V 20 2.9 V 10 0 0 100 200 300 400 500 600 700 800 Elapsed time [hr] Ouput PWM 2 @ 30 kHz Duty cycle of a pulse-width modulated fibre- optic transmitter for different input voltages 80 1.9 V as a function of time, (a) with a 5 kHz 70 carrier signal, (b) with a 30 kHz carrier recovery signal. 60 ] 50 % 40 0.8 V Duty cycle [ 30 20 10 b 0 0 100 200 300 400 500 600 700 800 Elapsed time [hr] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 As can be seen in the first two figures , the transfer function of the PWM, which is the duty cycle of its output as a function of the input voltage, remains remarkably stable up to 10 MGy at 5 kHz, with a minor decrease between 1 and 4 %. At 30 kHz we observe however a growth of the duty cycle for the lower input voltages, while the pulse width remains stable up to higher doses (> 6 MGy) for the higher input values. Therefore, one can conclude that the PWM is still operational at 10 MGy, but only for higher input voltages (> 2.0 V). This could be explained by a shift of the reference voltage for the comparator, which first affects the lower input voltages. Our in-situ measurements with both carrier signals show that this link is a suitable option for the transmission of slowly varying sensor signals (e.g. temperature, position,...) in a harsh environment, with optical multiplexing possibilities. Moreover, the overall radiation induced loss stems from the individual contributions measured separately and during previous experiments, which can be attributed in part to the driver current source and its amplifying stage, as well as to the optical power losses in the pigtailed laser diode (cf. picture below). Hence, we do not observe additional radiation damage due to the system integration. Output link 2 at MGy dose level 0.07 0.06 .) u . 0.05 a r ( e w 0.04 l po ca i t 0.03 p o ted 0.02 0.01 Transmit begin 0.00 end -0.01 0E+00 1E-04 2E-04 3E-04 4E-04 5E-04 6E-04 Time [sec] Comparison of the pre- and post-irradiation output signals of a pulse-width modulated optical transmitter, with a carrier signal of 5 kHz. After a cumulated dose of 10 MGy, we observe a radiation induced optical loss of about 7 dB. Future developments Demonstrate the feasibility of transmitting sensor signals to the control room,within a harsh environment,with multiplexing functionalities inprototype mock-up, that allows us to study ITER relevant position sensors. We therefore selected different position sensors, including limit switches, a resolver and a LVDT (Linear Variable Differential Transformer) sensor. Their signals will be conditioned and multiplexed, before transmission (to the control room) with both an electrical and an optical bus for comparison. Further developments will also include the testing of alternative components to implement both the PWM and the VCSEL driver, e.g. with SiGe technology. Moreover, the radiation tolerance of long-wavelength single mode VCSELs (~1,2-1,6 µm) should be assessed, since this would enable WDM (Wavelength Division Multiplexing) architectures with available and radiation tolerant single mode devices. Main contact person Marco Van Uffelen, [email protected] Main reference M. Van Uffelen, A. Giraud, F. Berghmans, "High gamma dose assessment of a multimode analogue fibre optic transmitter", Proceedings of the RADECS 2004 Conference, September 22-24, 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 OPTICAL FIBRES FOR FUSION PLASMA DIAGNOSTICS SYSTEMS Background The condition to achieve and maintain the ignition of a thermonuclear fusion plasma ignition calls for the construction of a large scale fusion reactor, namely ITER. This reactor is designed to deliver an average fusion power of 500 MW. The burning of fusion plasma at such high power level will release a tremendous amount of energy in the form of particle fluxes and ionising radiation. This energy release, primarily absorbed by the plasma facing components, can significantly degrade the performances of the plasma diagnostic equipment surrounding the machine. To ensure a correct operation of the Tokamak we need to develop highly radiation-resistance devices. In plasma diagnostic systems, optical fibre is viewed as a convenient tool to transport light from the plasma edge to the diagnostic area. Radiation affects the optical performances of the fibre mainly by the occurrence of radiation-induced absorption (RIA) and luminescence (RIL). Both effects degrade the light signal used for plasma diagnostic. SCK•CEN is currently assessing radiation-resistant glasses for optical fibres and is developing the associated qualification procedure. Objectives increase the lifetime of optical components in high radiation background; development of radiation resistance optical fibre capable to operate in the radiation background of ITER. Principal Results In the previous R&D activities supported by the European Fusion Development Agreement, we already pointed out the outstanding radiation-tolerance of high-OH content hydrogen-treated optical fibres. In the following-up of this radiation-hardening approach, we aimed at mastering the hydrogen-loading process by means of orientation irradiations and optimisation of the treatment parameters, i.e. pressure, temperature and treatment time. The radiation resistance assessment of optical fibres was carried out in the in-core irradiation facility SMIRNOF installed in the BR2 reactor at SCK•CEN. Iirradiation facility SMIRNOF. It consists of an in-pile section that can be installed in any BR2 reactor irradiation channel. The in-pile section supports inside a removable irradiation basket of 60 mm diameter. The fibres are coiled on the irradiation basket. The temperature of the fibres is actively controlled during the reactor operation by means of pressurized air-flow cooling system. Depending of the fibre size the radiation optical properties can be measured in 5 to 10 fibres simultaneously. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 30 OH vibration band RIA band B/m] 20 Low OH fibre With H2 ation [d attenu duced 10 n Low OH fibre i n No H2 atio i Rad 0 400 600 800 1000 1200 1400 1600 1800 Wavelength [nm] Spectral comparison of the RIA (radiation-induced absorption) response of the same glass low-OH content fibres. One of the two fibres is treated by hydrogen. Both fibres are subjected to identical fission reactor irradiation conditions 17 2 (7.12x10 n/cm (En>0.1MeV) and gamma ionising dose of 23 MGy. The lowest RIA is measured in the hydrogen treated glass. The graph also depicts the conversion mechanism between radiation-induced at 600 nm and the associated OH vibration bands). As shown in the figure, our last results show that the hydrogen-treatment technique can also be successfully applied to low-OH content optical fibres protected by an aluminium coating. The graph compares the RIA of two identical low-OH optical fibres except that one of the two is treated by hydrogen. A reduction of absorption as large as 5 can be observed as at 600 nm in the hydrogen-treated samples. Because of the low OH content nature of the fibres both fibre samples do not show the associated OH absorption vibration band at 1390 nm before irradiation. However as shown in the graphic, the OH-vibration band shows up during irradiation but only in the low-OH fibre treated by hydrogen. For the first time this observation clearly supports the conversion model stating that the radiation defect responsible for the RIA at 600 nm convert into OH groups under the action of hydrogen. When the hydrogen is exhausted the optical fibre ceases to be radiation-resistant. Contact Persons Benoît Brichard, benoî[email protected], Alberto Fernandez Fernandez, [email protected] Main References B. Brichard, A. Fernandez Fernandez, H. Ooms, F. Berghmans, M. Decréton, A. Tomashuk, S. Klyamkin, M. Zabezhailov, I. Nikolin, V. Bogatyrjov et al., “Radiation-hardening techniques of dedicated optical fibres used in plasma diagnostic systems in ITER”, Journal of Nuclear Materials, Vol. 329-333, pp 1456-1460, 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 RADIOACTIVE WASTE AND CLEAN-UP DIVISION Guy Collard RADIOACTIVE WASTE & CLEAN-UP DIVISION Guy Collard Scientific Staff Guy Collard, Patrick De Boever, Larissa Hendrickx, Paul Janssen, Natalie Leys, Max Mergeay. Supporting Staff Ilse Coninx, Annik Dams, Carine Van Reybroeck. Nuclear Chemistry and Services Department Scientific Staff Mireille Gysemans, Edward Helsen, Peter Thomas, Marleen Van Bocxstaele, Peter Van Bree, Ludo Vandenweyer, Frank Vanderlinden, Léon Vandevelde, Karel Van Gils, Frans Ven. Supporting Staff Gustaaf Geenen, Luc Gelens, Patrick Lycke, Wendy Mentens, Magda Ooms, André Stubbé, Karolien Van Rompaey, Kurt Verheyden, Els Verheyen, Hennie Warmoes. Site Restoration Department Scientific Staff Johan Braet, Aimé Bruggeman, Serge Bodart, Eric Cantrel, René Cornelissen, Jérôme Dadoumont, Yves Demeulemeester, Luc Denissen, Kris Dylst, Olivier Emond, Alfons Fonteyne, Patrick Goethals, Sven Harnie, Nathalie Impens, Patrick Maris, Luc Noynaert, Luc Ooms, Charles Plateau, Mathieu Ponnet, Frederik Slachmuylders, Jan Swinnen, Pierre Valenduc, Jan Vanhees, Winand Van den Rul, Vera Verstraelen, Isidoor Verwaest, Liliane Vos. Supporting Staff Eric Aegten, Gerard Castelyns, Peter Claes, Johan De Cock, Paul De Craecker, Stefan Dekelver, Danny Geerinckx, Bart Gilissen, Anja Haesen, Victor Helsen, Marco Mei, Henri-Rose Meynen, Roger Moelans, Roger Nijs, Jan Nuyts, Dominic Palinckx, Daniël Penneman, Joannes Pouders, Dirk Quirijnen, Jan Ruts, Sally Schraeyen, John Seghers, Wilfried Smolders, Erik Snoeckx, Ronny Van Bael, Sven Vanderbiesen, Robert Vandevoorde, An Vanhoof, Jo Van Laer, René Van Sweevelt, Tom Vernelen, Tom Verstappen, Nadine Verstraelen, Roger Weytjens, Ben Wuyts. Valorisation Department Scientific Staff Vincent Massaut Waste & Evacuation Department Scientific Staff Marc Aertsens, Wim Bastiaens, Thomas Beauwens, Frédéric Bernier, Gunther Bombaerts, Paul Borgermans, Marc Buyens, Christelle Cachoir, Pierre De Cannière, Maria De Craen, Grégory Delécaut, Hendrik De Soete, Frank Druyts, Matej Gedeon, Diederik Jacques, An Janssen, Bruno Kursten, Serge Labat, Karel Lemmens, Xiang Ling Li, Dirk Mallants, Norbert Maes, Jan Marivoet, Pol Meynendonckx, Kristiaan Moerkens, Valérie Moise, Hugo Moors, Bernard Neerdael, Lorenzo Ortiz Amaya, Véra Pirlet, Brigitte Pitz, Fabian Rorif, Sonia Salah, Steven Smets, Alain Sneyers, Xavier Sillen, Elie Valcke, Maarten Van Geet, Marc Van Gompel, Pierre Van Iseghem, Jan Verstricht, Geert Volckaert, Lian Wang, Eef Weetjens, Isabelle Wemaere. Supporting Staff Patrick Boven, Ben Gielen, Alex Isenborghs, Sabrina Lunardi, Tom Maes, François Slegers, Frank Vandervoort, Monique Van Geel, Maria Van Gompel, Louis Van Ravestyn, Wim Verwimp, Regina Vercauter, Bert Vreys. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 RADIOACTIVE WASTE & CLEAN-UP: INTRODUCTION Guy Collard The primary mission of the “Radioactive Waste and Clean-up” division is to propose, develop and assess solutions for a safe, acceptable and sustainable management of radioactive waste. Managing the past and preparing the future. For existing waste, this mission implies the development of long term management infrastructure insuring a minimum impact of activities of mankind on future generation (safe, reliable and socially acceptable disposal). In 2004 and in January 2005, two Belgian local communities - the communities of Dessel (Stola) and Mol (Mona) accepted to offer a solution for the long-term management of low-level and short-lived waste. In support of NIRAS/ONDRAF's assignment, SCK•CEN has developed research activities in parallel along three main lines for many years: hydro geological studies, combined disposal concept studies and performance assessment studies. For sure this scientific base of the project played an important role in the acceptation process. Because performance assessments are often black boxes for the public, demonstration is needed for the acceptation of geological disposal of high active waste. Therefore SCK•CEN, NIRAS/ONDRAF and EIG EURIDICE join their effort to demonstrate the feasibility of geological disposal of radioactive waste and spent fuel in Boom clay. A first step of this demonstration is the PRACLAY project. The objectives of the PRACLAY project are the demonstration of the reference design for vitrified HLW, as well as the characterization, verification, confirmation and demonstration of relevant elements of the disposal system and their behavior by means of a combination of small surface and large in situ experiments. As Research Center we wonder if alternative management of difficult waste should not be possible. Therefore we examine or develop new conditioning techniques to allow the responsible bodies to enlarge their scope and to make the best choice. It is the reason why we are testing new conditioning methods for bituminized waste and for radioactive sodium. We believe that nuclear energy will be necessary for the sustainable development of mankind in the 21st century, but we well understand that it would not be maintained if it is not proven that within benefits of nuclear energy a better protection of the environment is included. Although the current waste management practices are both technically and from the environmental point of view adequate, efforts in relation to future power production and waste management technologies should be put on waste minimization. Therefore, the new and innovative reactors, fuel cycle and waste management processes and installations should be designed so that the waste generation can be kept in minimum. In addition to the design, the installations should be operated so as to create less waste; consideration should be given e.g. to keeping water chemistry clean and to other quality factors. SCK•CEN in general and the "Radioactive Waste and Clean-up" division in particular are present in international groups preparing the development of innovative nuclear reactors. In this sense, our "Nuclear Chemistry" department develops analytical techniques for radioactive isotopes and stable chemicals, which got a low priority in the past but which could be considered as important by the future generations in charge of the disposal of high radioactive waste produced in the 20th century. For the decommissioning of existing nuclear facilities, we develop, demonstrate and apply techniques leading to an optimum between the minimization of the quantities of produced waste and their long term management. This leads to the development of appropriate decontamination techniques, but also to the development of conditioning technologies allowing to avoid controlled discharges of radioactive wastes in the environment for economical reasons. In this sense, we adapted the well-known technique of High Pressure Jet Cutting to large contaminated equipment and successfully applied it to the dismantling of SCK•CEN's BR3 reactor. Because we believe that our planet is a village and that safety and sustainable development cannot be realized just by solving local problems, we follow the evolution of an enlargement of present international collaboration (e.g. "regional repository" for waste disposal). Moreover we deal our knowledge by participating in many exchange and experts groups of international institutions (IAEA, NEA, European Commission). We also consolidated bilateral cooperation with Japan, France, the Netherlands and new members of the European Union. Contact Guy Collard, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 CELLULOSE-CONTAINING WASTE AND BITUMINISED SALTS Background In Belgium, Medium-Level radioactive Waste (MLW) would be eventually disposed off in an underground repository in a geological formation such as the Boom Clay, which is studied as a reference host rock formation. MLW contains large quantities of non-radioactive chemicals that are released upon contact with pore water. It could be the case, for instance, for plutonium bearing cellulosic waste – such as paper tissues used to clean alpha glove boxes – issued from nuclear fuel fabrication (BELGONUCLEAIRE). At high pH, as in a disposal gallery backfilled with cement, the chemical degradation of cellulose will generate water-soluble products that may form strong complexes with actinides such as Am, Pu, Np, and U. This could lower the sorption of these elements onto the clay minerals, and hence increase their migration through the clay barrier. Another chemical perturbation could occur from the ~3000 m3 of so-called Eurobitum bituminised MLW, with precipitation sludges from the chemical treatment of spent nuclear fuel, and containing about 750 tons of NaNO3. The presence of NaNO3 in this waste will give rise to several processes susceptible to affect the safety of the disposal system. Amongst others, it is necessary to verify that the swelling pressure of bitumen on the gallery wall and the osmotic pressure within the near-field are not too high to induce a fissuration of the host rock, leading to the formation of preferential migration pathways. Objectives The major objective of our work is to obtain a broad understanding of the different processes induced by the release of non-radioactive chemicals in the clay formation, to assess the chemical compatibility of different MLW forms with the clay. Principal results For cellulose-containing waste, according to the results of our degradation, solubility, and sorption experiments, we could confirm that α-ISA (α-isosaccharinic acid) is the most important cellulose DP (degradation product). Its concentration in the disposal galleries will likely be limited by its strong sorption onto cement and by precipitation of Ca-isosaccharinate. We have also observed that both exaggeratedly high and more realistic concentrations of α-ISA, or other cellulose DPs, did not significantly affect the sorption of Pu(IV) and Am(III) on alkaline-plume altered Boom Clay (pH set at 11 in our experiments) and on undisturbed Boom Clay (pH ~8.2). Finally, we estimate from our experiments that α-ISA complexes of actinides formed at pH 12.5 should dissociate when they will reach the undisturbed clay, due to (i) the decrease of the pH to ~8.2, and (ii) the strong sorption of actinides onto Boom Clay. Therefore, we do not presently consider the leaching of cellulose DPs as a major concern. ) 30000 g / l m 25000 ( t Am, BC en 20000 ci i f Am, APA BC ef 15000 Pu, BC co n 10000 o Pu, APA BC i t rp 5000 o S 0 RCW DP a-ISA 0.2 mM a-ISA 1 mM a-ISA 8 mM Type of contacting solution Sorption coefficients (ml/g) for americium and plutonium in Boom Clay (BC, pH 8 – 8.5) and alkaline-plume-affected Boom Clay (APA BC, pH 11) in Real Boom Clay pore Water (RCW), and in RCW containing cellulose degradation products (DP) or pure α-isosaccharinic acid (a-ISA), for a clay-to-solution ratio of 1 g per 5 ml. For this clay-to-solution ratio, a sorption coefficient of 1000 ml/g means that for every 10000 atoms of, for instance, 241Am, 9950 atoms are sorbed on the 1 g of clay, and 50 atoms are in the 5 ml of solution. For a sorption coefficient of 10000 ml/g, only 5 out of the 10000 atoms are in the 5 ml of solution, the remaining 9995 atoms being sorbed on the 1 g of clay. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 For bituminised waste, first hydro-mechanical scoping calculations indicate that, for the case of final disposal in the Boom Clay, the bitumen swelling pressure due to uptake of water by the de-hydrated salts has to stay below the limit of ~8 MPa. The preliminary results of two laboratory osmosis tests on small clay cores and of a first in situ osmosis experiment suggest that the osmotic pressure is limited to only a few meters water column. Until now, no fundamental flaws were identified regarding the compatibility of EUROBITUM in view of its final disposal in an argillaceous host rock. 4.5 radial displacement at gallery wall (m) 4 0.5 3.5 0.4 3 0.3 0.2 2.5 0.1 2 0 1.5 -0.1 45678910 1 0.5 0 -0.5 45678910111213 applied swelling pressure (MPa) Calculated evolution of the radial displacement of an underground disposal gallery wall as a function of the applied swelling pressure, for a disposal gallery of 5 m internal diameter, with presumed more realistic conditions: imperfect plasticity – drained boundary condition – coupled storage coefficient. Future work Modelling of the speciation of U, Th, and Np in Boom Clay pore water in the presence of α-ISA, to confirm that this cellulose degradation product will not affect the migration behaviour of these nuclides Further compatibility studies on Eurobitum waste (ageing, swelling, pressure build-up ...) to provide sufficient scientific data on the compatibility of Eurobitum with an argillaceous host formation. Main contact person Elie Valcke, [email protected]. Main reference Rorif F. and Valcke E. (2004) The effect of cellulose degradation products on the sorption of Pu and Am in alkaline plume affected Boom Clay. Final Report to ONDRAF/NIRAS for the contract N° CCHO-95/268. Restricted Report R-4057, 2004, SCK•CEN, Mol, Belgium. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 A NEW MULTICOMPONENT VARIABLY SATURATED FLOW AND TRANSPORT MODEL Background The migration of many naturally occurring elements and contaminants in soil and sediments is affected by a multitude of complex, interactive physical, chemical, mineralogical, and biological processes. Computer simulation of the interaction of these processes requires a coupled reactive transport code that integrates the physical processes of water flow and advective-dispersive solute transport with a range of biogeochemical processes. Such coupled codes are necessary tools for evaluating waste management and pollution control scenarios. Objectives The objective is to develop, test, and apply a new reactive transport code that is the result of coupling two existing codes: the water flow and solute transport code HYDRUS-1D (Šimůnek et al., 1998) and the geochemical code PHREEQC-2 (Parkhurst and Appelo, 1999). This new code, called HP1, expands significantly the possible applications of the individual codes by integrating water flow, solute transport, heat transport and biogeochemical reactions. The advantage of such coupled codes is that for example, relationships between changing flow conditions (from saturated to unsaturated flow and vice versa) and chemical conditions (from reducing to oxidising, or from low to high pH and vice versa) are accounted for (Fig. 2b). This allows a more accurate description of the migration of metals and radionuclides in the subsurface environment Principal results Soil Profile depth (cm) 0 Organic Matter Water Phase Air Phase A 7 E 19 H H+ K NaOH Bh1 24 H H+ Bh2 28 Site 1 Mg Br- Bh/C Ca K+ Cd2+ 50 Cd + C1 H H+ OH- 75 H Na H+ H ZnCl2 H H+ Site 2 H H+ C2 Ca H+ Zn + ... Cl- H H H+ (a) H H H+ H + + CdCl Site 6 H H + H Na 500 H Zn2+ H H+ e + ) H H m ac 400 f c r ( u il Cation Aqueous o s 300 Actual surface flux e s Exchange Speciation v o ti (P - E ) t 200 act (c) a l in u x m u 100 l Potential surface f u C flux (P - Epot) 0 1972 1974 1976 1978 1980 1982 Time (year) (b) Fig. 1. Schematic overview of the example simulating long-term transient flow and transport of major cations and heavy metals in a soil profile. The top-left figure shows a podzol consisting of 7 soil horizons with different physical and chemical properties. The upper boundary conditions are obtained by subtracting the potential evaporation Epot (based on time series of weather data for the Campine region, Belgium between 1972 and 1982) from the precipitation P (bottom left figure). The actual flux (precipitation P minus actual evaporation Eact, the latter is dependent on the available water in the soil profile) is larger since Eact is smaller than Epot. The right figure illustrates the formation of aqueous complexes and the exchange of cations with a multi-site cation exchange complex associated with the soil organic matter. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Water Content pH 0.26 0 0 4.4 0.4 5 0.22 4.2 0.36 pH -2 -2 ent 4.5 0.18 4 ont 0.32 h (cm) h (cm) c 4 3.8 pH r 0.28 -4 0.14 -4 ept ept te 0.24 3.5 D D 3.6 Wa 0.1 Water Content 0.2 3 -6 -6 3.4 0.06 3.2 Cl 1975 1976 1977 1978 1975 1976 1977 1978 10-4 Cd s Time (year) Time (year) 3 -2 0.02 Cl 10 Cd 10-5 Log(aqueous Cl) (mmol/kg soil) Log(Aqueous Cd) (mmol/kg soil) queou -3.8 A 0 -0.8 0 10-3 10-6 -4.2 1972 1974 1976 1978 1980 1982 -1.1 -4.6 Time (year) -2 -2 -5 (cm) -1.4 (cm) -4 -4 epth epth -5.4 D -1.7 D (a) -5.8 Fig2. Calculated time series of water -6 -2 -6 -6.2 content and pH (top figure) and Cl 1975 1976 1977 1978 1975 1976 1977 1978 -2.3 Time (year) Time (year) -6.6 and Cd concentrations (mmol/kg soil, bottom figure) in the Bh1- hi t22 d th (b) Space-time plots of some key variables in the A-horizon illustrating the interactions between water flow (drying of the soil during summer), solute transport (upward transport of Cl during summer) and geochemical reactions (increased Cd concentration due to the formation of the aqueous complex with Cl). The high Cl concentration during summer increases the mobility and bioavailability of Cd in the soil profile. HP1 has been extensively tested using the original codes and a different reactive transport code (i.e., CRUNCH, with the limitations that only steady-state flow is possible, Steefel and Yabusaki, 1996). The one- dimensional HP1 code is able to handle a variety of processes required to simulate the migration and fate of multiple solutes in soils and sediments. Main processes are transient water flow in variably saturated porous media for different boundary conditions (e.g., daily values of the actual surface flux, Fig. 1b), convective and conductive heat transport subject to time-variable temperatures at the soil surface, advective, dispersive and diffusive solute transport including physical nonequilibrium solute transport, and low-temperature geochemical reactions based on thermodynamic equilibrium, kinetics or mixed equilibrium-kinetic reactions (e.g., formation of metal complexes, such as cadmium – chloride complexes, Fig. 1c). HP1 supports aqueous speciation reactions, multi-site cation exchange (e.g., on the soil organic matter of a Podzol soil, Fig. 1c), equilibrium and kinetic dissolution and precipitation of minerals, and sequential and parallel networks of user-defined kinetic reactions. Specific for soil systems, HP1 allows atmospheric upper boundary conditions (involving precipitation, evaporation, and transpiration), water uptake by roots and spatial variability in physical and geochemical properties (e.g., due to soil layers, Fig. 1a). The figures 1 and 2 illustrate a HP1 application in which the long-term transient flow and transport of major cations and heavy metals in a soil profile are simulated. Although the example considers metal leaching from a soil contaminated by atmospheric deposition, the new code can also be used to address diffuse or local soil pollution by radionuclides. Further applications include radionuclide uptake by plant roots, calculation of acid mine drainage from rock piles or mine tailings, chemical evolution in the near field of a repository, etc. Future developments In the near future, additional geochemical processes will be included such as oxidation/reduction reactions, surface complexation and solid solutions. The main expected applications are in the field of simulating the mobility and bioavailability of major cations, heavy metals, pesticides, anions (e.g., nitrate) and radionuclides, in a groundwater – soil – plant system. Main contact person Diederik Jacques, [email protected] Main reference D. Jacques, J. Šimůnek, D. Mallants, M.Th.,Genuchten, 2003. The HYDRUS-PHREEQC multicomponent transport model for variably-saturated porous media: Code verification and application. MODFLOW and More 2003: Understanding through Modeling, Conference Proceedings, ed. E. Poeter, Ch. Zheng, M. Hill, and J. Doherty. IGWMC, Colorado School of Mines, 23-27. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 A POOR SEALING SCENARIO FOR DEEP DISPOSAL OF HIGH LEVEL WASTE Background Especially for geological disposal options in clay, the safety of the repository relies chiefly on the performance of the host formation as the main barrier. Understandably, scenarios in which this clay barrier is somehow bypassed earn great concern in PA (Performance Assessment) studies. The PSS (Poor Sealing Scenario) is one of those scenarios that have been recently studied by the PA section of the Waste & Disposal department in the framework of the Belgian programme on deep disposal of high-level radwaste in Boom Clay. This scenario hypothesises that at least one disposal gallery and an access shaft have been poorly sealed off, providing a preferential pathway for RNs (radionuclides). The scenario further assumes a severe climate change, which would invert the presently downward hydraulic gradient, such that the potential impact would be maximal. Objectives The main objective is assessing the contribution from two transport processes to the overall radionuclide migration from a spent fuel repository towards the Neogene aquifer. The processes considered are advective transport through the poorly sealed repository and diffusive transport through the host formation. In addition, we would like to identify the most influential parameters with respect to repository design and performance. Principal results A B shaft A transport gallery disposal gallery Left: reference situation considered in Poor Sealing Scenario calculations: It is assumed that one of the disposal galleries (∅=2.2 m; l=200 m) is poorly sealed. Furthermore, the shaft (∅=6 m; l=40 m) is assumed to be poorly sealed as well. Both are connected through a transport gallery (∅=3.5 m; l=156 m). Other disposal galleries are not shown in the picture. The thickness of the Boom Clay layer is conservatively assumed to be 80 m and the shaft is in direct contact with the Neogene aquifer. Right: fields of hydraulic potential (m) at steady state (top) and 129I concentration (Bq/m3) 8000 years after canister failure (bottom). At present, the hydraulic gradient over the Boom Clay layer is very small and oriented downward. As such, even if we conservatively assume that the hydraulic conductivity of the galleries and shaft is several orders of magnitude larger than that of Boom Clay, these conductive features will not provide a preferential pathway. However, when the gradient is inversed, for instance in case of a severe climate change (e.g. glaciation), the poorly sealed galleries will act as a large drain in the formation and RN fluxes into the Neogene aquifer could be increased. In this study, we assumed an inversed hydraulic gradient of 0.05, which presumably is an extremely conservative value. Because of the small gradient across and the low hydraulic conductivity of the host formation, which is supplying the water, the flow rate through a very conductive repository is still very small, i.e. around 100 litre/year for a 200 m disposal gallery. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 6.0E+06 1.0E+06 10k years 5.0E+06 50k years 1.0E+05 ) ³ 100k years m q/ ) 1.0E+04 B 4.0E+06 y ( ion (Bq/ t a 1.0E+03 r 3.0E+06 ux t n Fl e I 9 c n 2.0E+06 12 1.0E+02 o I c 9 12 Boom Clay contribution 1.0E+06 1.0E+01 shaft contribution 0.0E+00 1.0E+00 1.0E+08 1.0E+06 10k years 1.0E+07 Boom Clay contribution 50k years ) ³ 1.0E+05 shaft contribution 100k years m 1.0E+06 / total q ) B 1.0E+05 y 1.0E+04 n ( q/ o i B ( at r 1.0E+04 1.0E+03 ux ent 1.0E+03 C Fl 1.0E+02 14 conc C 1.0E+02 14 1.0E+01 1.0E+01 1.0E+00 1.0E+00 1.0E+07 1.0E+06 10k years 1.0E+06 ) ³ 50k years 1.0E+05 m / 100k years q 1.0E+05 ) (B 1.0E+04 q/y n o i 1.0E+04 (B t disposal gallery a r 1.0E+03 ux t l 1.0E+03 en transport gallery Tc F nc 1.0E+02 1.0E+02 99 co c T 1.0E+01 99 1.0E+01 shaft Boom Clay contribution shaft contribution 1.0E+00 1.0E+00 1000 10000 100000 1000000 10000000 0 50 100 150 200 250 300 350 400 Time (years) distance along advective pathway (m) Left: concentrations along the advective pathway for 3 characteristic RNs in the Poor Sealing Scenario. Right: RN fluxes into the Neogene aquifer under Poor Sealing conditions. Advective contributions via the shaft are limited. Only for relatively short-lived RNs characterised by a substantial fraction instantaneously released upon canister failure, such as 14C, the total flux is somewhat larger compared to the NES. Transport simulations with non-sorbing, non-solubility-controlled RNs characterised by a relatively slow release from the waste matrix, such as 129I, revealed that the impact of a PSS on the performance of the repository is very limited. However, in the case of relatively short-lived (in geological timescales) RNs where a considerable amount of the inventory is quickly released, such as 14C, the releases from the shaft pathway can amount to about the same order of magnitude as the normal diffusive path through the host formation. The evaluation of solubility controlled radionuclides, such as 99Tc, revealed that a PSS is not a problematic scenario as the concentration downstream of a disposal gallery is always inferior to the product of the flow rate by the solubility limit, whatever the inventory of the considered element in the gallery. As the Boom Clay acts as a considerable diffusive sink for RN all along the advective pathway, it was observed that a small increase of the length of that pathway led to a significant decrease of RN releases. Future developments The developed model can now be used to optimise the design of the repository. In addition, the competition between advection and diffusion was found to be especially challenging for the classical numerical tools and could be explored in further benchmark exercises. Main contact person Eef Weetjens, [email protected] Main reference X Sillen,.E. Weetjens, J. Marivoet. "Consequence analysis of a sealing defect in a spent fuel repository in Boom Clay (poor sealing scenario)." SCK•CEN, Mol, (BLG report to be published - 2005). www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 THE MOCK-UP “OPHELIE” A DEMONSTRATION FOR HLW DISPOSAL Background The waste management agency NIRAS/ONDRAF detailed the first architecture for the disposal of vitrified HLW (high level radioactive waste) in the early 1990’s. It consisted of a network of disposal galleries in the Boom Clay formation, the reference host formation in Belgium. In such gallery the waste packages were positioned in a central liner. Bentonite based blocks backfilled the space between the central liner and the gallery lining. A large scale in situ test called PRACLAY will simulate a section of such a gallery in the HADES (High Activity Disposal Experimental Site) underground research facility. During the preparation of this test, the principal investigators realised that several aspects needed to be worked out in detail further through a large scale mock-up at the surface. EIG EURIDICE (an economical interest consortium between SCK•CEN and NIRAS/ONDRAF) managed this mock-up test, called OPHELIE; it consisted in the design, operation and analysis of the mock-up. Other partners in this research project were CEA, UPC, EDF, and ANDRA. Objectives Realising the mock-up test has enabled us to study the feasibility of the different technical aspects of the repository design, such as manufacturing and installation of the backfill material in preparation of the PRACLAY In Situ Test. Running the OPHELIE mock-up test then has revealed the performance and the THM (thermo- hydro-mechanical) behaviour of the different components, as well as the robustness and reliability of the monitoring equipment. An extensive analysis of the components (backfill, instrumentation, metals) during and after dismantling has completed the information obtained during the previous stages. Principal results Mock-up during assembly; precompacted backfill blocks around the central liner; hydration tubes at the outside of the backfill (with a void between backfill and outer liner) and the sensor cables. backfill blocks central tube with heater hydration tubes and external void 160 136 °C Temperature evolution in the middle section of 140 the mock-up, with a maximum temperature 120 near 140°C, and the quick initial heating and 117 °C final cooling phases. 100 °C , ure t a r 80 mpe Te 60 90° TC35 - 254 mm TC36 - 333 mm TC37 - 442 mm 40 180° TC38 - 580 mm 0° TC39 - 759 mm 20 TC40 - 873 mm TC41 - 996 mm 270° 0 15-Apr-98 01-Nov-98 20-May-99 06-Dec-99 23-Jun-00 09-Jan-01 28-Jul-01 13-Feb-02 01-Sep-02 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 void filled by bentonite Backfill block pattern recovered during dismantling; the swelling hydration tube hydration tube has closed the 36 mm void near the hydration tube, as well as void filled by bentonite the joints between the blocks. original backfill blocks original backfill blocks Microscopic analysis (SEM and EDX) of strain gauge components to investigate corrosion processes. SEM-2, 150× SEM-1, 10× EDX-1 EDX-2 After the conclusion of the preliminary investigations (such as the development of the backfill material), and the assembly of the test set-up (shown in the first picture), we started with the hydration phase at the end of 1997. Half a year later, the heating started, and increased step-wise (see temperature evolution graph). The heating ended four years later (end of August 2002), and after a cooling period of some six weeks, we dismantled the mock-up in October 2002, followed by a in-depth analysis of the samples taken. THM-modelling works were carried out in parallel to allow for a better interpretation of the measurements and observations. An extensive characterisation of the original (non-exposed) backfill material delivered us the necessary input model parameters. In general, the backfill behaviour was satisfactorily. The third picture, taken during dismantling, shows a clear swelling pattern, with all installation voids filled, thereby creating a low-permeability environment around the central tube. A low swelling pressure and a high apparent thermal conductivity were other important observations. During the test, several observations on corrosion and water chemistry lead to a closer look on chemical and microbiological phenomena, including geochemical modelling. The hydration of the backfill created less favourable chemical conditions, such as high chloride concentrations, which were detrimental to some sensors. The last figure shows a typical result of the corrosion analysis. We also observed some bacterial activity in the colder part of the experimental set-up. Future developments The results are an important issue in the current review of the disposal design. A new temperature criterion is now considered in the repository design: the maximum temperature in the engineered barriers must be kept below 100°C. We also take into account the lessons learnt from the sensor and corrosion analysis (picture) for the design of the monitoring of the underground PRACLAY Heater Test, to be installed in 2007. Main contact person Jan Verstricht, [email protected] Main reference J. Verstricht, H. Van Humbeeck, X. L. Li, P. De Cannière, Final report on the mock-up “OPHELIE”, EIG EURIDICE (to be published in 2005). www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 ALKALINE PLUME IN BOOM CLAY CORES: THE ECOCLAY-II EUROPEAN PROJECT Background The degradation of cementitious materials used in large quantities to backfill the galleries of medium level waste repositories in deep geological formations will release hyperalkaline fluids rich in alkaline cations (K+ and Na+) and calcium. It will modify the chemistry of the interstitial water of the host rock close to the galleries and induce mineralogical transformations that could affect the retention properties of the geological barriers. Objectives The aim of the Ecoclay-II project (Effects of Cement on Clay barrier performance) was to assess the effect of an alkaline plume on the chemical and mineralogical properties of the clay and on the migration of the radionuclides released from a cementitious repository into clay. To identify and to assess the extent of the phenomena and processes which could influence the clay chemistry and the radionuclides migration, percolation experiments have been performed on Boom Clay cores with two different types of synthetic cement water: young cement water (pH ~ 13.5) and evolved cement water (pH ~ 12.5). The concentrations of the main components of the percolated fluids (major cations, major anions, organic matter, electrical conductivity, and pH) were measured as a function of time. These results were used as experimental reference and compared with the predictions of the chemical-coupled transport codes used in order to assess the various approaches followed by the different modelling teams. Principal results Numerical simulations are useful to discriminate between different conceptual models to identify the active geochemical processes that could explain the perturbation of Boom Clay by an alkaline plume. Beside some poorly recognized mechanisms, a large source of uncertainties with geochemical modelling and reactive transport is that many parameters remain also unknown, especially those related to the dissolution kinetics of primary minerals (a.o., the rate constants and the effective reactive surface area of minerals in compact clay). However, sensitivity studies may help to identify the most important processes. Figure 1 shows the effect of cation exchange and kinetics of dissolution / precipitation on the pH of the outflow water. 14 14 (a) (b) 12 12 pH pH 10 10 no cation exchange with phillipsite single site cation exchange without phillipsite multisite cation exchange 8 8 0 1020300 102030 PoreVolume Pore Volume Figure 1: Evolution of pH in the outflow solution during percolation of young cement water through a Boom Clay core (inflow solution with an initial pH of 13.5). The numerical simulations (a) presented on the left side are only based on cation exchange mechanisms. Taking also into account kinetics of minerals dissolution, and secondary phases precipitation greatly improves the modelling results (b) (experimental data are shown as points, model predictions as lines). The calculated pH is in better agreement with the measurements when dissolution / precipitation kinetics are also considered in the model. Figure 2 shows the results of two simulations made for K+ and Na+ concentrations in the percolated water with and without considering phillipsite, a potassium-containing zeolite, often used in other modelling studies as secondary phase to account for K+. With phillipsite the K+ concentrations increases much more slowly because of the K+ uptake in the solid phase, but the simulation does not properly describe the final concentration plateau for K+ and Na+. Omitting phillipsite in our calculations provides better results for K+ and Na+, without adverse effect on the calculated pH (see Fig. 1). www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 6000 ) -1 l g m 4000 ( n + o K i with phillipsite at r t with phillipsite en 2000 without phillipsite nc Co without phillipsite 0 0102030 Pore Volume + Figure 2: Concentrations of K+ and Na+ in the outflow of a percolNaation experiment with young cement water through a Boom Clay core. The numerical simulations combine here cation exchange and kinetics of minerals dissolution / precipitation. Phillipsite, a K-zeolite, often used in other modelling studies as secondary phase to control K+, does not improve our simulation results but have no adverse effect on the calculated pH as seen in Fig. 1 (experimental data are shown as points, model predictions as lines). Presently, the predictions of the chemical-coupled transport codes succeed to provide correct orders of magnitude of the concentrations measured in very complex geochemical systems. For instance, the calculated values of the plateau of the concentration curves reached after steady-state are now in reasonable agreement with the experimental data. However, the simulations of chemical transients remain very often problematic and deserve further developments to identify the relevant processes still ignored and omitted in the present models. Future developments From an experimental point of view, a detailed mineralogical characterisation of Boom Clay exposed to an alkaline alteration is still missing to better understand poorly known processes presently lacking in the models. It remains a.o. necessary to identify some neoformed secondary phases whose detection is a technical challenge, such as zeolite and calcium-silicate-hydrate (CSH phases). From the modelling side, efforts are still needed to improve the conceptual models to take into account the remaining but not sufficiently known processes. For instance, by including potentially relevant mechanisms not yet presently considered, such as dissolution of organic matter at high pH, dissociation of aluminol and silanol groups on the clay lateral edges, and to tests other clay assemblages that could also control CO2 in the Boom Clay system. For this purpose, the recently updated Boom Clay reference database will be used and benchmarks between different reactive codes will be performed. Main contact persons Pierre De Cannière: [email protected] Jacques Diederik: [email protected] Lian Wang: [email protected] Main references Andra (2005) Ecoclay II: Effects of Cement on Clay Barrier Performance – Phase II. Final Report. EC project N° FIKW-CT-2000-00028; Andra report N° CRPASCM04-0009, 381 pp. Wang L., De Cannière P., Jacques D., Moors H., Van Gompel M., and Aertsens M. (2004) Experimental and modelling studies of Boom Clay exposed to an alkaline perturbation. R-4019, SCK•CEN, Mol, Belgium, 35 pp. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 BOOM CLAY PORE WATER AT THE MOL SITE STATUS 2004 Background Boom Clay has been studied for over 25 years as a potential host rock for the final disposal of radioactive waste. To assess the safety of Boom Clay (also mentioned as BC) as a main barrier to the release of radionuclides, a good understanding of its geochemistry is essential. Objectives The main objectives are to evaluate the existing techniques to obtain representative BC pore water samples, to determine the spatial variation of the BC pore water composition, and to establish a coherent geochemical model for explaining the present BC pore water composition. It is also aimed to propose a reference BC pore water composition to be used in the laboratory experiments, for speciation calculations, and for assessments of perturbation of Boom Clay. Principal results a b c (a, b) Example of a piezometer. This piezometer is composed of a cylindrical ceramic filter screen mounted on a supporting PVC tube. Pore water is collected in a chamber behind the filter screen. Two small diameter water pipes enable to bring the pore water from the host rock to the underground laboratory where it is collected in sampling containers prior to chemical analyses (c). Pore water sampling is realised in situ from piezometers, or by the mechanical squeezing or the leaching of clay cores in the laboratory. These three sampling techniques were compared and evaluated. As evidenced by this study, piezometer water is the most representative for the in situ conditions. Squeezed water is representative when considering the major ionic composition, but not for trace elements and organic matter. Finally, batch leaching experiments reveal a very different composition, but when the samples are carefully ultra-filtered, a comparable major cation composition is measured. The Boom Clay pore water at the Mol site is a NaHCO3 solution of 15 mM with an important amount of dissolved organic matter (about 100 mg C / l). The redox potential (Eh) of Boom Clay is about -300 mV, probably controlled by the equilibrium of pyrite and siderite under the in situ geochemical conditions. The total alkalinity of Boom Clay pore water is 15 mM and is about equal to the carbonate alkalinity. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Gas-phase (CO2) sampling level Sample loop: Routine water analyses T - pH The PEGASUS experimental set-up establishes the simultaneous measurement of pCO2, pH, temperature and pore water composition. This allows to better define the system and to evaluate the system equilibrium state unambiguously. Being very important parameters, the Boom Clay pH and partial CO2 pressure (pCO2), and their controlling mechanisms are still not fully understood. Both pH and pCO2 measurements are technically challenging because of the loss of gaseous CO2 if Boom Clay is in contact with air. Apart from the well known in situ ARCHIMEDE-argile measurement (pH 8.2), the new in situ measurement (pH 8.0) demonstrated the technical difficulties in pursuing a reliable quality pH measurement. Alternatively, the pH is obtained through speciation calculations, suggesting a pH range of 8.3 to 8.6. The calculated pCO2 value for the latter pH range is between 10-2.4 and 10-2.8 atm. Recently, a new technique is developed for a more accurate and representative measurement of in situ pCO2, pH, temperature and water composition (the PEGASUS experiment). A geochemical model is proposed and explains well the observed pore water composition in terms of major - 2- ions (Na, K, Si, Ca, Mg, Fe, HCO3 , SO4 ). This model is based on chemical principles of ion exchange and mineral dissolution/precipitation and is therefore able to predict the variations of the Boom Clay pore water composition under varied conditions. A reference water composition is calculated according to the observed Boom Clay mineralogy and the pore water characteristics. Future developments A systematic follow-up of the pore water composition, with a systematic set of analyses and a centralised database is necessary to study the variability of the pore water composition, to follow the evolution of the perturbations, to improve the statistical dataset, and to calibrate the geochemical model in a wider range of conditions. Main contact person Mieke De Craen, [email protected] Main reference De Craen M., Wang L., Van Geet, M. & Moors H. (2004) "The geochemistry of Boom Clay pore water at the Mol site", status 2004. SCK•CEN Scientific Report. BLG 990. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 NON-DESTRUCTIVE RADIOLOGICAL CHARACTERISATION OF CONTAMINATED AND ACTIVATED CONCRETE Background The decommissioning of nuclear facilities leads to large quantities of concrete and building material wastes. Radioactivity in building structures arise from very different physical processes such as neutron activation (bioshield), diffusion of the contaminants in the material (primary coolant leakage, maintenance and fuel loading) or aerosol deposition. The variety of the building material also extends the range of faced radiological characteristics. Therefore the minimization of concrete waste generation requires extensive characterisations and the availability of different measurement tools and methods. Up to now, these measurements came from the coring and the radiological analysis of the concrete, which is a destructive, long and costly technique. Looking for alternative solutions, SCK-CEN has started to investigate in collaboration with EDF-R&D and CEA (France) several non destructive methods based on gamma spectroscopy and different spectral examinations using mathematical calibration and modelling tools available on the market. Information on in-depth activity distribution can be derived from in situ gamma spectra by modelling absorption laws (peak to peak ratios) and photons interactions (Compton front) in the bulk of the concrete. Objectives As they combine modelling and measurement, the different methodologies being evaluated involve a lot of uncertainty sources linked to the measurement environment, to the knowledge available on site (historical background, material composition), to the operator responsible for the data acquisition and to the performance of the equipment. Therefore a detailed sensitivity analysis is required to define the range of applicability and the performances of the different methods. Principal results Spectra acquisition Modelling parameters - circular surface located at Focus ing coordinates X,Y - background measurement - Collimation geometry Shield ing ISOCS Modelling - Material composition - Focusing - Thickness - Shielding - Density - Source - Geometry ISOCS Calculation Source - Efficiency curve : from 45 keV to - Surface area Characteristic 1500 keV - Source/detector position length L - Extrapolation down to 30 keV - Material composition - Contamination/activation profile (i.e. exponential ) Spectra analysis software - Activity in emission peak i (Ai) - Ratios Ai / Ak (Ak = key line activity) For a given multi-energetic isotope : Ai = f(L) The iterative ISOCS methodology for multi-energetic isotopes For multi-energetic isotopes, a method based on iterative efficiency curve calculation using ISOCS calibration software has been developed and firstly tested on deeply activated concrete (Bioshield). The main activation products 152Eu, 154Eu and 133Ba are ideal candidates to investigate the performances of this method since they have several high yield energy lines spread over the operating range of the chosen Germanium detector and their distributions in the bulk follow exponential laws A(z)=A(0)*e-z/RL (attenuation of a thermal neutron beam). The relaxation lengths (RL) and therefore the in-depth distribution profiles found for 133Ba show a very good agreement (within 10%) with the measurements done on core samples. Isotopes www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 with very different activation cross sections (like 133Ba and 152Eu) may have different exponential distributions and require specific model optimisation. Investigations around the in situ assessmentof the contamination depth have so far been restricted to the ISOCS methodology applied to the 32 and 661 keV emissions of 137Cs daughter. Indeed in situ as well as core sample measurements confirm that 60Co precipitates at the concrete surface and is not a suitable contamination tracer. However quantitative evaluation of penetration depth of 137Cs is made difficult by multi- parameters distribution profiles depending on concrete physical state (cracks, protective layer ...), high uncertainty on extrapolated detector efficiency below 45 keV and the large influence of the radiation background. The ISOCS methodology developed is firstly tested ex situ to avoid the influence of high radiation background 4.0E+06 3.5E+06 3.0E+06 2.5E+06 Ba-133 : 81 kev line q) Ba-133 : 303 kev line ty (B i v Ba-133 : 356 kev line i t 2.0E+06 Eu-152 : 122 kev line ac Eu-152 : 779 kev line tal o T 1.5E+06 Eu-152 : 1408 kev line RL = 5 cm 1.0E+06 RL = 12 cm 5.0E+05 0.0E+00 0 5 10 15 20 25 30 35 Relaxation Length (cm) A(z)=A0 * exp(-z/RL) A consistent distribution profile is obtained when activities calculated on the different photopeaks are equal. Here the activation distribution is modelled by an exponential decrease(1 parameter). Future work While activation depth can be assessed In situ with a low uncertainty thanks to the availability of suitable tracers, the measurement of the penetration depth of 137Cs with the multi-energetic approach is still imperfect. Characterisation of the detector in the low energy area and optimisation of the measurement configuration (narrow collimation without "pin-hole effect") could reduce the uncertainty on 32 keV calculated efficiency and appreciably improve the performance of the technique. Exploitation of the 661 keV emission Compton front using Monte Carlo modelling should be investigated to provide a palliative solution when 32 keV activity cannot be calculated, e.g in baryte concrete, where natural Ba isotopes also emits 32 keV X- rays. Main contact person Eric Cantrel, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 WATER DETRITIATION: BETTER CATALYSTS FOR LIQUID PHASE CATALYTIC EXCHANGE Background Fusion reactors are our hope for a clean nuclear energy. But as they shall handle huge amounts of tritium, -1 -1 1.5E19 Bq GWth a or about 50 000 times more tritium than light water fission reactors, they need detritiation. Most tritium losses can be trapped as or can easily be transformed into tritiated water. Water detritiation is preferably based on the multiplication of the large equilibrium isotope effect during the exchange reaction of tritium between hydrogen gas and liquid water in a counter current trickle bed reactor. Such LPCE (Liquid Phase Catalytic Exchange) requires an efficient hydrophobic catalyst. SCK•CEN invented and developed such a catalyst in the past. In combination with an appropriate wettable packing, different batches of this catalyst performed very well during years of extensive testing, allowing us to develop the ELEX process for water detritiation at inland reprocessing plants. Objectives • To reproduce and possibly improve the SCK•CEN catalyst for tritium exchange between hydrogen and liquid water; • To demonstrate the high overall exchange rate and thus high detritiation factors that can be realized with it in a small and simple LPCE column under typical but conservative operating conditions. Principal results F Schematic overview of the installation for testing LPCE catalysts: the hydrogen flow-rate is tritiated in the bubble bed reactor, which is filled with an excess tritiated water and catalyst. We measure the rate of detritiation in the trickle bed reactor, which contains the to-be-tested catalyst. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 140% 120% e th ). 100% e to iv (% t e 80% typ rela 60% tivity c a t s e reference 40% ly th ta f ca o 20% ty in i se tiv c 0% a crea 5R18* 10R18 5R-289 MO1254 MO1255 In -20% -40% Different types of catalysts Compared to the already good performing SCK•CEN reference catalyst (5R18), the catalyst with 70 % (w/w) PTFE (5R18*) performed somewhat worse. Doubling the amount of platinum from 1 % (w/w) to 2 % (w/w) (10R18), resulted in an increase of catalyst performance of only 20%. The best result was obtained with a type of catalyst based on a different support material (MO1254, MO1255), performing about a factor two better than the reference. (Working conditions: 40°C, gas flow rate: 10 mol/(m².s), liquid flow rate: 3 mol/(m².s), activity of to be detritiated hydrogen around 75 kBq/mol.) In collaboration with Johnson Matthey and E-vision we reproduced the SCK•CEN catalyst. It is prepared by depositing platinum on an activated charcoal support before mixing it with PTFE (polytetrafluorethylene) as a hydrophobic material. With a view to test this reproduced and different new types of catalysts for LPCE, the SCK•CEN tritium laboratory was improved by installing a bench scale set-up with a 2 cm diameter 50 cm long counter-current trickle bed LPCE column, equipped with the necessary control and measuring systems for studying the catalytic exchange rate of tritium between hydrogen and liquid water. In combination with the catalyst an appropriate wettable stainless steel packing is used. The reproduced SCK•CEN catalyst, has been tested at SCK•CEN, D. Mendeleev University in Moscow and at the Tritium Laboratory of the Forschungszentrum Karlsruhe. Similar results found in the different institutes, confirmed the historical performances of the SCK•CEN catalyst, our maintained ability to prepare it and the good performance of the test installation. During following tests, different types were investigated to determine the influence of the amount of platinum, PTFE, different types of support material and particle size of the Pt/C catalyst. To compare the different catalysts, experiments were done at a constant set of working conditions, at two temperatures, 40°C and 60°C, and in a trickle bed LPCE column with a homogeneous catalyst/packing (etched stainless steel spirals) mixture in a ratio ½. The overall exchange rate constant of all types of catalyst which were tested was high. For one type of catalyst it was even roughly two times better than for the reference type. Future developments By extrapolation, these new results would allow us to obtain, at 40°C and under analogous conditions as before, a decontamination factor of 10 000 with a column of about 3 meters long. Such performances would make this catalyst an excellent candidate for application at JET or ITER, and SCK•CEN is willing to commercialise this catalyst. But extrapolation of results obtained in a column of 0.5 m should be confirmed experimentally. We have started to demonstrate together with the National Institute of Cryogenics and Isotope Technologies in Romania that our (improved) catalysts are physically stable and that they allow high, constant and reproducible overall tritium exchange rates between hydrogen and liquid water for a longer period of time in a longer column. Main contact person Johan Braet, [email protected] Main reference A. Bruggeman, J. Braet, S. Vanderbiesen, “Water Detritiation: Better Catalysts for Liquid Phase Catalytic Exchange”, Fusion Science & Technology, American Nuclear Society, to be published. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 MALTENE AND SOLUBLE SALT REMOVAL FROM BITUMINISED RADIOACTIVE WASTE Background According to the present Belgian reference scenario, Eurobitum bituminised waste is to be disposed off in a deep underground repository in a stable geological formation such as Boom Clay. This waste originates mainly from mixtures of nuclear fuel decladding slurries and waste concentrates from the nuclear fuel cycle. In Belgium, a weight ratio of 60/40 bitumen/waste was applied. The bitumen used as waste matrix is a commercial blown bitumen, type R85/40. Most of the inorganic waste particles are homogeneously incorporated in the bitumen matrix and are smaller than 40µm. Safety performance studies on gas generation, effect of degradation products with complexing properties, generation of a swelling-pressure build-up due to water uptake of the dehydrated salts, and the reaction of the leached NaNO3 with the surrounding Boom clay are in progress. Even though these studies up till present do not show that this waste is unacceptable for deep underground disposal, we investigate a low temperature method to recondition the bituminised waste, just in case it would be decided not to dispose the waste as such in a deep underground repository. The method is based on the removal of the majority of the compounds that are the most sensitive towards radiolysis (i.e. saturated hydrocarbons – these are mostly present in the maltene fraction of bitumen) on the one hand and on the removal of hygroscopic water-soluble salts (mainly NaNO3) on the other hand. The pie chart on the right shows the main fractions maltenes present in Eurobitum. When the maltenes and the asphaltenes soluble salts can be removed and destroyed, the final 20% insoluble salts waste contains only the asphaltenes and insoluble soluble salts salts with the major part of the radionuclides. The 40% separation scheme below shows how to separate the 18% waste in these fractions. The separation of the maltenes from the precipitated asphaltenes and salts 22% is based on an existing deasphalting process used in the petroleum industry, but has to be adapted to the case of Eurobitum waste. This scheme is also adaptable to other types of bituminised waste. Eurobitum bituminised waste composition Dissolved maltenes 1) + solvent 2) + non-solvent Bitumen-salt 3) solid-liquid mixture separation Precipitated Asphaltenes + salt 4) + water (ultrasound -treatment) 5) solid-liquid separation Asphaltenes + insoluble salt Dissolved salt Separation scheme of the bituminised radioactive waste www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Objectives The aim is to diminish the volume and stabilise the bituminised waste, with a minimisation of the radionuclides in the maltene fraction and the aqueous solution. Therefore, we need to understand the mechanisms and experimental variables governing the distribution of the elements among the asphaltene, maltene and aqueous phases. In 2004 we searched for an appropriate solvent – non-solvent combination for the maltene separation step, applicable on large scale, respecting nuclear and chemical safety guidelines. Principal results The experiments were performed using self-made non-radioactive waste simulates with a composition comparable with the real Eurobitum waste. In the first place, we searched for an easy way to determine the purity of the separated maltene phase. We tried to monitor the separation by turbidimetry of waste – solvent – non-solvent mixtures as a function of time and sample height. A quasi inverse relationship between the purity of maltenes on the one hand and the settling velocity of the asphaltenes on the other hand is observed. This inverse relationship enables to predict roughly the maltene purity from simple turbidimetric experiments. The most important variables governing the settling velocity and the relative amount of maltene ash were the concentration of bituminised waste and the solvent/non-solvent ratio. The best separations (with the quickest settling) were obtained using a low bituminised waste concentration in combination with a volumetric solvent/non-solvent ratio of 10/6. This is shown in the 3D graph . An elemental analysis of the ashes was performed using SEM-EDX. Within the limit of the standard error, the relative composition of the maltene ash was constant over the complete range of the studied variables. 12.00 10.00-12.00 10.00 ) 8.00-10.00 h 6.00-8.00 8.00 mm/ ( 4.00-6.00 y t 2.00-4.00 ci 6.00 o l 0.00-2.00 e 4.00 g v lin t t e 2.00 s 0.00 8.33 10:12 16.6 10:10 10:8 g ( 33.3 olv bit -s um 50.2 10:6 on en v/n +s 10:4 ol alt s ) 3D graph of the settling velocity as a function of the amount of bituminised waste added to 100 mL solvent on the one hand and the solvent/non-solvent volumetric ratio on the other hand. Future Developments Instead of measuring the settling velocity of the asphaltenes, we will follow the settling of radionuclides in activated samples. These tests will give more detailed information on the interaction of radionuclides with asphaltenes. This method will be more sensitive to determine the expected purity of the maltenes. We will also try to improve the quality of the aqueous secondary waste. Main contact person Nathalie Impens, [email protected] Main reference N. Impens, J. Van Laer, L. Vos, A. Leenaers, A. Fonteyne, P. Thomas, P. Van Bree, S. Dekelver, R. Vandevoorde, "Maltene and soluble salt removal from bituminised waste simulates: fractionation of the waste elements", Energy & Fuels, American Chemical Society, article in press (2005). www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 BR2 DIVISION Pol Gubel BR2 Operation Scientific Staff André Beeckmans, Willy Beets, Henry Blowfield, Simon Claes ,Willy Claes, Jozef Cools, Bernard Coupé, Luc De Laet, Jan Dierckx, Edmond Essers, Eugeen Essers, Peter Gerinckx, Geert Geubbelmans, Freddy Geenen, Eduard Geysen, Pol Gubel, Eric Jennen, Silva Kaltcheva, Edgar Koonen, Vadim Kuzminov, Richard Liesenborgs, Fernand Mallants, Dirk Meynen, Marcel Noël, Bernard Ponsard, Karel Van Eyndhoven, Marcel Van Hoolst, Dirk Vanleeuw. Supporting Staff Armand Aerts, Davy Aerts, Walter Aerts, Monique Alen, David Bastiaensen, Tom Berghmans, Danny Boonen, Filip Borgers, Geert Broeckx, Kris Bruns, Werner Cauwenberghs, Gert Cools, Leon Cools, Gert Curinckx, Ferdi Daemen, Chris De Wandeleer, Arne Deckx, , Patrick Geboers, Freddy Gevers, Hektor Gevers, Gerard Groenen, Luc Hallaert, Dirk Jansen, Gudrun Joyeux, Kris Meynen, Bert Moons, Patrick Nijs, Luc Overath, François Poorters, Stijn Slegers, Patrick Smeyers, Richard Stappers, Tom Stappers, Kristof Stessens, Kamiel Swinnen, Kris Thys, Guido Van Clemen, Wim Van de Craen, Bart Van de Venne, Dirk Van Gestel, Jan Van Gompel, Aloïs Van Hoolst, Steven Van Loven, Marc Vanrintel, Frans Vansummeren, Tom Verachtert, Kurt Verstreepen, Leo Verwimp, Benny Vullings, Emiel Willekens, Bart Wilms, Gunter Wilmsen, Koen Wuyts. Reactorexperiments Scientific Staff Philippe Benoit, Camiel Decloedt, Jean Dekeyser, Ludo Dekien, Guido Engelen, Philippe Gouat, Patrice Jacquet, Steven Mellemans, Frank Mertens, Felix Put, Frans Schelles, Jef Valenberghs, Walter Vennekens, Ludo Vermeeren, Alfons Verwimp, Marcel Wéber, Stefan Wirix. Supporting Staff Luc Drooghmans, Herman Lodewijkx, Victor Oeyen, Rachel Verboven, Rob Wens. Maintenance BR2 Scientific Staff Stefan Declercq, Marc Hannes, Stefan Lodewyckx, Filip Ramaekers, Bart Smolders, Roger Stynen, Jan Van der Auwera. . Supporting Staff Willy Dierckx, Johan Fransen, André Gastmans, Valère Jacobs, Guido Lievens, Rudy Linden, Henri Meeus, Christiaan Mertens, Wim Minnen, Didier Mortiers, Jozef Sannen, Freddy Van Diepenbeek, Hendrik Van Gestel, Herman Van Houdt, Luc Van Roy. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 BR2: INTRODUCTION Pol Gubel The Reactor BR2 traditionally provides irradiation services for its internal (within SCK•CEN) and external clients. The services supplied range from the neutron and gamma irradiations of materials and fuels within the framework of scientific programs belonging to the internal and external customers, to commercial productions in the field of radioisotopes for medical and industrial uses and NTD-Silicon for the microelectronic industry. These commercial activities are exclusively directed to external customers and are of prime importance to provide financial support for the operating costs of the reactor. For some years we try to exploit our know-how gained from the operation of the reactor by promoting services specifically oriented to the safety and operation of existing research reactors and the development of new ones. These efforts were fully realized for the first time in 2002 and 2003 by two contracts related to the behavior under irradiation of structural materials and the development of new fuels. A third program was launched end of 2004 aiming at the in-pile qualification of a replacement fuel for a future research reactor. It is expected that this qualification program will be extended for some years. Also the synergy between our knowledge in irradiation technology and the scientific collaboration with external partners led to the development and the successful irradiation of new and first of its kind irradiation rigs for the in-situ testing of materials. After a previous successful demonstration with in-situ uniaxial testing, we built in 2004 a new device and the required out-pile equipment to investigate in-situ the dynamic effects of cyclically applied stresses on fusion materials. The first of this kind irradiation is foreseen early in 2005. Development work on new concepts for ramping fuels was continued in 2004. Two concepts are in development using a variable neutron screen on one hand and the strong flux gradient across a peripheral 200 mm channel on the other hand, with the possibility of combination of both concepts in one single device. In the frame of an EC funded project, metallurgical samples will be irradiated under Pb-Bi. Specially designed capsules are foreseen for the Callisto loop and a new gas capsule is being designed for irradiation at higher temperatures. The irradiation program is planned to start in Callisto late in 2005. Nowadays the irradiation programs require a very specific description of the irradiation conditions that they will be subjected to. For this reason, we have developed an in-house competence for reactor physics at BR2 which has involved the implementation of the required computational tools. These tools are now being systematically used for prediction and evaluation of irradiation conditions of all experiments. Major evaluations conducted in 2004 concern new fuel and material irradiation programs in Callisto, preparation and follow-up of an irradiation program of advanced MTR fuel, the optimization of irradiation devices containing Pb-Bi and of a new pool-side facility for production of NTD-Silicon, and more specific BR2 evaluations as the detailed heat flux distributions in standard BR2 fuel elements in function of different parameters. In 2005, beside the evaluations needed for new programs, a number of evaluations will be needed in the framework of the 2006 decennial safety reassessment of the BR2 facility. Advanced irradiations in research reactors require the on-line monitoring of crucial parameters like neutron fluxes, gamma dose rates, central fuel rod temperatures, fission gas release pressures and small geometry changes. Our activities in this field aim at a detailed understanding of the sensor behavior in the irradiation conditions in order to extract reliable real-time information. Major work performed in 2004 concerned the testing in various conditions of new miniaturized fission chambers in collaboration with CEA and the assessment of radiation-induced electromotive forces in mineral-insulated cables. Future work will concern the study of on-line fast neutron flux measurements with dedicated miniature fission chambers and in-pile measurements on test fuel rods. These activities in reactor physics and in-core instrumentation are part of a global programmed that allows us to fully exploit the exceptional capabilities of the reactor facility. This programme also deals with the development of data/acquisition systems and of new multipurpose reusable irradiation devices. All instrumented irradiation devices are now connected to an in-house built data acquisition system allowing the scientific researchers and the project engineers to follow their experiments on-line using their office PC’s. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 The CALLISTO loop is still our most important irradiation facility for materials and fuels experiments. It comprises three in-pile sections that are connected to a common out-pile equipment. The principal purpose of this device is to simulate the irradiation conditions representative of PWR reactors. One of the in-pile sections is completely inserted within the reactor core to maximize the fast flux conditions. The main activities in 2004 concerned the irradiation of various structural materials for PWR and Fusion reactors, the start of an important fuel program subsidized by the EC, comprising 8 instrumented (gas pressure and central temperature) and 8 non-instrumented fuel pins. We foresee in 2005 the further utilization of the CALLISTO loop for testing of materials and the continuation of the fuel program started in 2004. The exploitation of the reactor was very successful in 2004. The availability of the plant reached 96.65 %, no incident was recorded and the commercial revenues reached a new record. In collaboration with the SCK•CEN's Physical Control, we proposed and obtained the approval of our Licensing Authority for a detailed action plan in the frame of the 2006 decennial safety re-evaluation: the main objective is to guarantee the operational safety and the reliability of the facility until at least 2016 as decided by the board of governors of the SCK•CEN. For 2005 we foresee again various maintenance and equipment replacement activities to guarantee a continued safe and reliable operation for the future: the greatest efforts will be focused on the preparation of the replacement of the displacement control rod mechanisms and the primary pumps of the Callisto loop. Contact Pol Gubel, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 OPERATION OF THE BR2 REACTOR Background The BR2 is still SCK•CEN's most important nuclear facility. After an extensive refurbishment of 22 months to compensate for the ageing of the installations, to enhance the reliability of operation and to comply with modern safety standards, it was restarted in April 1997. The facility is mainly used for the irradiation and testing of fuels and materials and for commercial productions – including radioisotopes for the medical and industrial uses, and NTD-Silicon. Objectives To keep the reactor facility available for the scientific irradiation programmes and commercial productions along the whole predefined operation schedule, while maintaining safety during operation as the top priority. Principal results The reactor was operated for 113 days at the mean power level of 56 MWth. The normal operation period was extended for a week during the summer to optimise the production of radioisotopes for the radiopharmaceutical industry. The reactor was operated with an availability of 96.65 % (time at power over scheduled time at power). One interruption of operation was recorded due to a control rod drive mechanism and caused a delay of two days in the operation schedule. Another two days interruption of the operation was due to a malfunction on the feed-bleed control system of the CALLISTO loop. General view on the process control room www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Plant Operation Data Year Availability % 1998 99,94 1999 99,97 2000 93,05 2001 96,15 2002 100,00 2003 97,81 2004 94,78 Plant operation data Routine maintenance activities and inspections during the scheduled shutdowns guarantee the continued safe and reliable operation of the facility and provide the basis for a secure long-term future. Recurrent problems on control rod drive mechanisms are now being fixed by systematic control and replacement of critical components. New control rod drive mechanisms should be put into service from 2006 on. The evacuation of fuel elements to Cogema-La Hague continued with one transport of 68 fuel elements. In total, from 1998, we had 17 transports for 1054 fuel elements. After a successful qualification program launched in 2003, an order was placed with CERCA for the fabrication and delivery of a first full batch of high density fuel elements with a reduced (73%) enrichment In collaboration with the SCK•CEN's Physical Control, we proposed and obtained the approval of our Licensing Authority for a detailed action plan in the frame of the 2006 decennial safety re-evaluation: the main objective is to guarantee the operational safety and the reliability of the facility until at least 2016. Future developments For 2005, we foresee: a standard operation schedule with an extra week of operation for the cycles 02 and 03/2005; various maintenance activities aiming at maintaining a secure and reliable operation; one transport of spent fuel elements to Cogema-La Hague; to start various activities (studies, inspections, maintenance...) as foreseen in our action plan in the frame of the 2006 decennial safety re-evaluation. Main contact person Pol Gubel, [email protected] Main reference E. Koonen, F. Joppen, P. Gubel, "Safety challenges encountered during the operating life of the almost 40 years old research reactor BR2", IAEA-CN-82: International Conference on Topical Issues in Nuclear Safety, 3-6 September 2001, Vienna, Austria. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 BR2 REACTOR: MEDICAL AND INDUSTRIAL APPLICATIONS Background The radioisotopes are produced for various applications in the nuclear medicine (diagnostic, therapy, palliation of metastatic bone pain), industry (radiography of welds, ...), agriculture (radiotracers, ...) and basic research. Due to the availability of high neutron fluxes (thermal neutron flux up to 1015 n/cm².s), the BR2 reactor is considered as a major facility through its contribution for a continuous supply of products such 99Mo (99mTc), 131I, 133Xe, 192Ir, 186Re, 153Sm, 90Y, 32P, 188W (188Re), 203Hg, 82Br, 41Ar, 125I, 177Lu, 89Sr, 60Co, 169Yb, 147Nd, ... Neutron Transmutation Doped (NTD) silicon is produced for the semiconductor industry in the SIDONIE (Silicon Doping by Neutron Irradiation Experiment) facility, which is designed to continuously rotate and traverse the silicon through the neutron flux. These combined movements produce exceptional dopant homogeneity in batches of silicon measuring 4 and 5-inches in diameter by up to 750 mm in length. Objective To provide a reliable and qualitative supply of radioisotopes and NTD-silicon to the customers in accordance with a quality system that has been certified to the requirements of the "EN ISO 9001: 2000". This new Quality System Certificate has been obtained in November 2003 for the "Production of radioisotopes for medical and industrial applications" and the "Production of Neutron Transmutation Doped (NTD) Silicon" in the BR2 reactor. Principal results Evolution of the Income from Radioisotopes and NTD-Silicon Production in the BR2 Reactor 400 350 s 300 it n n i 250 e U e m v 200 i o t c la 150 In e R 100 50 0 1997 1998 1999 2000 2001 2002 2003 2004 Years NTD- Silicon Radioisotopes + NTD-Silicon Evolution of the income from radioisotopes and NTD-silicon production in the BR2 reactor 1. Since the restart of the BR2 reactor in 1997, after its refurbishment in 1995-1997, the income from the production of radioisotopes and NTD-silicon increased considerably as shown in the figure above in relative units. 2. The loading of an additional PRF irradiation device in the reactor in 2004 enhanced the position of BR2 99 on the European market for the production of Mo (T1/2=66 h), which is the major isotope produced in 99 99m the BR2 reactor for the manufacture of Mo/ Tc (T1/2=6 h) generators. 3. BR2 has consolidated its market position in the production of large quantities 'high specific' activities of 192 Ir (T1/2=74 d) for both therapeutic and industrial applications. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 4. Highly enriched 176Lu targets are routinely and successfully irradiated for the production of 177Lu, which is an ideal candidate for future targeted radiotherapy with radiolabelled peptides: long half life (T1/2=6.71 d), good physical properties, emitting both beta (maximum 0.5 MeV; average 0.17 MeV) for therapy and gamma rays (113 keV and 208 keV) useful for imaging. 5. BR2's silicon irradiation service performed very satisfactorily throughout 2004 in terms of its level of business and the record income that it generated. Handling of irradiation baskets in the reactor main pool Future Developments 188 188 188 1. BR2 is working on a project to supply W (T1/2=69.4 d) for the manufacture of W/ Re generators. 188 Several medical applications of Re (T1/2=16.9 h) are actively under consideration in cardiology and bone pain palliation. 2. The present irradiation capacity for NTD-silicon is booked out for 2005. The ongoing study to identify the technical feasibility of new schemes to increase BR2's NTD-silicon capability by more than 100%, whilst also taking into account the industry increasing demand for 6-inch irradiation capacity, will be finalised. A positive decision to build a new facility is expected after production of a favourable business plan. Main contact person Bernard Ponsard, [email protected] Main references B.Ponsard, J.Hiltunen, P.Penttilla, H.Vera Ruiz, A.L.Beets, S.Mirzadeh, F.F. (Russ)Knapp. “The Tungsten- 188/Rhenium-188 Generator: Effective Coordination of Tungsten-188 Production between the HFIR and BR2 Reactors”, 4th International Conference on Isotopes, 4ICI, Cape Town, South Africa, March 10-14, 2002. Published in the Journal of Radioanalytical and Nuclear Chemistry (JNRC), Volume 257, Number 1, pp. 169- 174, July 2003. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 BR2 REACTOR: IRRADIATION OF FUELS Background Safe, reliable and economical operation of reactor fuels, both UO2 and MOX types, requires in-pile testing and qualification up to high target burn-up levels. In-pile testing of advanced fuels for improved performance is also mandatory. Objectives Neutron irradiation of LWR (Light Water Reactor) fuels in the BR2 reactor under relevant operating and monitoring conditions, as specified by the experimenter's requirements. Improvement of the on-line measurements on the fuel rods themselves Principal results Bottom of the OMICO instrumented fuel bundle. All pins are equipped with a central high temperature thermocouple connected via the lower end plug and a pressure transducer connected via the upper end plug In 2004 further development work was done for preparing the long term irradiation of LWR fuel in the high-pressure facility CALLISTO in the BR2 reactor. The irradiation of this experiment was started in November. Detail design work for the OMICO (Oxide fuels: MIcrostructure and COmposition Variations)-MIMAS-PV (MIMAS Process Variation) program has continued. A twin bundle consisting of 8 instrumented- and 8 non-instrumented fuel pins is being tested in the high-pressure high-temperature loop CALLISTO under typical PWR-conditions (155 bar, 300°C, controlled PWR water chemistry). The bundle comprises UO2, (U,Pu)O2 as well as (Th,Pu)O2 pins. Each of the pins in the upper part of the twin bundle is provided with a gas pressure transducer connected via the upper end plug and a high temperature thermocouple type W5/W26 connected via the lower end plug. A total number of 40 instrumentation wires are installed on the pins and in the upstream and downstream section of the fuel bundle. The lower basket containing the 8 non-instrumented pins can be removed for hot-cell examinations and coupled again to the upper basket. The irradiation can then be resumed with both the instrumented and the non-instrumented bundles. The picture shows a detail of the instrumented bundle. Special attention has been given to an accurate measurement of the power generated by the pins. Fourteen thermocouples are distributed along the twin-bundle for that purpose. MCNP calculations have been made and qualified by the irradiation in the CALLISTO loop of a mock-up of the experiment. This irradiation also allowed the determination of the heat generated by gammas as well as the heat losses of the in-pile section to the BR2 water. The leak rate via the coupling between non-instrumented and instrumented bundle has been determined in a water test. The out-of-pile equipment has been complemented by a system that enables the operators to take water samples even after a possible rupture of some pins. Such a failure can cause a considerable contamination of the cooling water of the CALLISTO loop. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Further details on the experimental program are reported in the chapter "Reactor Safety" of this report. : pressure tube fuel rod pressurized water Power Ramping - Scheme of the PWC/CCD device (Pressurized Water Capsule/ Calibration and Cycling Device) with axial reactor coordinates in mm (‘0’ being the centre of the 76 mm high BR2 core). In 2003 four power ramps have been done on BWR fuel segments in an in-pile pressurized water capsule. After the irradiation of the segments and their removal from the reactor, gamma spectroscopy measurements have been performed. The measured activity of certain isotopes of suitable half-life (e.g. 140Ba, 140La), taking into account the relevant part of the irradiation history, provides data on the time- averaged fission rate during a certain period or on the instantaneous fission rate for a certain reference reactor power. The average linear rod power assessed via this technique is in very good agreement with the values based on the thermal balance as calculated on-line during the execution of the test in the reactor (linear power from gamma spectro/linear power from thermal balance = 99.4 to 105.4%). Future Developments It is foreseen to irradiate the OMICO twin fuel bundle for achieving a burn-up of about 25 GWd/tM and 2-5% fission gas release. After the first irradiation cycle the set of non-instrumented rods will be unloaded to study critical fuel performance indicators (cladding corrosion, creep, fuel swelling) as well as to perform an independent experimental control of the power generated in the fuel rods by gamma spectrometry. These measurements will then be repeated after every irradiation period of 5 reactor cycles (21 days each). Main contact person Alfons Verwimp, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 BR2 REACTOR: IRRADIATION OF FUSION MATERIALS Background In collaboration with the EFDA (European Fusion Development Agreement), SCK•CEN irradiates several materials in the BR2 reactor at different temperatures and up to different doses to study their mechanical and physical properties during and after irradiation. Those materials are candidates for the construction of different parts of the ITER (International Thermonuclear Experimental Reactor) fusion reactor and of the long-term DEMO (DEMOnstration) reactor. Objectives to irradiate up to 2 dpa RAFM (Reduced Activity Ferritic Martensitic) steels joints and RAFM ODS (Oxide Dispersion Strengthening) at 300°C. to build and test an experimental rig to perform in-situ creep-fatigue tests under neutron irradiation and its out-pile equipments. to design a new irradiation basket to irradiate in BR2 copper/stainless steel joints and RAFM specimens with implanted helium at low dose. Principal results 1. Survey of irradiations in 2004 In 2004 we started the IRFUMA IV (IRradiation of FUsion MAterials) specimens irradiation. The materials involved in this experiment are the following: three different joints made of RAFM steel with denomination EUROFER97; i.e. Laboratory Mock-up, Laboratory Joint and Fusion Welded Joint , each material type specimen is placed in a separate needle. EUROFER97 ODS (EUROFER97 alloyed with 0.3% Y2O3 using the ODS manufacturing route) The irradiation is conducted at 300 °C in the D180 channel (IPS 2) of the CALLISTO loop in the BR2 reactor. The test section is shared with specimens irradiated within the MIRE-Cr (Modelling of IRradiation Effects on pure Fe-Cr-C alloys) experiment that is also a Fusion task. Some of the IRFUMA IV specimens www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 2. COFAT project The aim of the COFAT project (COpper FATigue) is to investigate in-situ the dynamic effects of cyclically applied stresses in the copper components of ITER on the neutron damage accumulation and to assess the mechanical performance during neutron irradiation. In 2004, we built the in-pile rig and the required out-pile equipment (pool water cooling loop, high pressure helium supply loop). The COFAT rig contains 2 creep-fatigue test modules designed in teamwork with VTT. Each module is made of 2 bellows (one to push and the other to pull on the specimen) and of one LVDT (Linear Variable Differential Transformer) to measure the gage length variations. Linear Variable Differential Transformer Fatigue Specimen Pull Bellows Push Bellows COFAT : creep-fatigue test module 3. ROBIN Basket We designed a new material irradiation basket. The aim of the ROBIN basket (ROtating Basket with Instrumented Needles) is to irradiate encapsulated specimens at low dose within the 90-600°C temperature range. The basket main characteristics are: 9 irradiation positions (rotating with the cooling flow), 2 instrumented irradiation positions (fixed in central area), easy loading/unloading during BR2 operation. 9 needles loaded with rotation inducers 2 instrumented needles encapsulated specimens ROBIN Basket Future Work continue irradiations of RAFM joints, MIRE-Cr and ODS specimens at 300°C up to 2 dpa. irradiation of copper alloys under creep-fatigue loading at low temperature in water (COFAT series) build and test the ROBIN basket. irradiations of copper/stainless steel joints at 150°C up to 0.1 dpa. irradiations of RAFM specimens with implanted helium at 60°C and 350°C up to 0.2 dpa. Main Contact persons Patrice Jacquet, [email protected] Wéber Marcel, [email protected] Main Reference Patrice Jacquet, September 2004, "In-situ investigation of the mechanical performance and lifetime of copper in a neutron environment", R-4004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 IRRADIATION OF LIGHT WATER REACTOR MATERIALS IN BR2 Background There is a constant need to evaluate the integrity and the behaviour of the structural materials used in Light Water Reactors (LWR's). With the CALLISTO facility operating at Pressurised Water Reactor (PWR) conditions, one can perform in-pile testing of structural materials from reactor pressure vessel and internal core components under representative conditions of temperature, pressure and water chemistry. The experiments generally aim at understanding the material degradation effects limiting the lifetime of the nuclear power reactor or requiring the replacement of specific components. A better understanding of material degradation is essential for the plant lifetime management and experimental proof of material properties is needed if extended life service is aimed at. Objectives Neutron irradiation of LWR materials in the BR2 reactor under operating and monitoring conditions which are representative for their in-service conditions. Improvement of the capability to measure on-line the significant parameters to provide the modelling codes developers and the material scientists with the most valuable data sets. Principal results 1. LIRES Experimental device Initially devoted for testing of high temperature reference electrodes in the framework of the LIRES-project, which is a European sponsored research program on reference electrodes, we also combined three other irradiation experiments in this integrated device: (1) investigation of the irradiation influence on the electrochemical corrosion behavior of fission material under appropriate water chemistry conditions, (2) study of the behavior of the sub-miniature 235U fission chambers, (3) validation of a new SCK•CEN electrical feedthrough, based on zirconium oxide. A newly developed feed-through system which was designed for the OMICO programme was in fact put in operation first in the LIRES project. It was manufactured and qualified according the ASME III class 1 rules, it allows the penetration of 40 instrumentation cables or tubes and the whole feedthrough system is reusable. Fission chambers SPND H2 detectors Corrosion electrodes Gamma thermometer SPND Reference Electrodes LIRES Rig Containing the 4 Experiments www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 The CALLISTO instrumentation feed through system; designed for the OMICO programme, it was first used in the LIRES experimental device. 2. TIHANGE III programme In order to produce useful data for the validation of the damage models at high fluences of the lower part of the Tihange III reactor pressure vessel, we irradiated base and weld materials from this reactor in the CALLISTO rig during one BR2 cycle, up to a fluence corresponding to roughly 60 years of irradiation in Tihange III. Given the large difference in neutron fluxes between the irradiations in BR2 and in the actual reactor, we have irradiated additional specimens at a lower flux level to assess the flux effect in material damaging. 3. MIRE-Cr programme The MIRE-Cr irradiation campaign is the experimental part of the scientific program "Modelisation of irradiation effects, modeling oriented experiments on pure Fe-Cr-C alloys". The experiment consists of a total of five irradiation cycles that started in the 5th BR2 cycle of 2004. The objective is to provide the necessary modeling-oriented experimental support for the validation of the existing tools. This would bring useful information on the way to model the irradiation damage, and even offer a good reference point to study the effect of additional elements, such as W, V, and Ta, on the defect accumulation behavior. We loaded 777 mini specimens from six different materials in the CALLISTO loop; the samples were encapsulated to prohibit reaction with the coolant and to control the temperature by making good use of gamma heating and thermal barriers. Watertight holders containing 12 x 20 TEM specimens Assembly of CT – specimens Detail of the MIRE-CR rig: part of the needle with CT and TEM specimens 4. GEISHA programme We irradiated a total of 478 specimens from 11 different types and from different steel materials for the "Institute For Materials Research" of Tohuku University during one cycle to reach a fast neutron (E > 1 MeV) fluence of 1.8 1020 n/cm². We assembled the specimens, most of which were encapsulated (like the MIRE-Cr experiment), to form 2 needles. Future developments Continuation of the MIRE-Cr to test irradiated specimens from a large range of fast neutron (E > 1 MeV) fluence: i.e. from 3.8 1019 to 5.6 1020 n/cm². Irradiation of mechanical specimens from the same batch as the cladding material of the LEMONIZ reactor vessel in IPS 2 of CALLISTO. Main contact person Marcel Wéber, Marcel.Wé[email protected] Main reference M. Wéber, R. W. Bosch, L. Vermeeren, "Design and Development of a Multipurpose PWR Rig for In-Core Instrumented Testing ", Int. Conf. Water Chemistry of Nuclear Reactor Systems" San Francisco, USA, October 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 NEW IRRADIATION INFRASTRUCTURES: FUEL TRANSIENT Background Transients can be required for fuel qualification. In this case, the fuel has to withstand a single transient in which the power is multiplied by a factor two or more in a fraction of one or a few minutes. Transients can also be required in order to investigate the physics of the fuel behaviour, such as the conditions of fission gas release, or the measurement of the heat conductivity. This type of research usually requires the execution of a succession of numerous small transients. The execution of power transients on LWR fuel rods is an activity which dates back in the seventies. Successful research programmes, such as DOMO (DOdewaard MOx), or HBC (High Burnup Chemistry), or, more recently GERONIMO, used the PWC (Pressurised Water Capsule) device, coupled with the CCD/VNS (Control and Calibration Device – Variable Neutron Screen). Objectives The refurbishment of existing installations was recently undertaken. A serious shortcoming of the CCD/VNS device is linked to the use of He-3 as removable neutron absorber. Tritium PWC top leaks plagued the operation of CCD/VNS for years. Instead of re- plug building the same installation, possibly with improved components but with the same trouble factor, we opted for the development of radically different concepts which would enable us to get rid of the VANESSA connection problem. BR2 channel Principal results penetration The solutions envisaged still use the successful PWC capsule and a modified CCD. We came with two very different concepts. VANESSA PWC pressure In VANESSA (VAriable Neutron Screen System with boric Acid), tube the removable neutron absorber is boric acid in water solution, BR2 channel circulating in a CCD-like screen. guide tube The transient is executed by the progressive replacement of the concentrated solution by a less concentrated solution – possibly Screen feed pure water. By adequate timing of flow control valves and/or lines injection pumps, it is possible to shape the ramp to a pre- determined profile. A device like VANESSA allows transient amplitudes of up to 3 times, when passing from almost saturated Beryllium boric acid solution to pure water. matrix Because VANESSA can be loaded in a 84-mm channel, the choice ∆T of the channel can further widen the range of initial / final Screen conditions that are achievable with the device. Boric acid does not produce active by-products and so, the tritium tightness problems that plagued the operation of the previous Fuel CCD/VNS are eliminated. The out-of-pile installation does not need anymore to be located in a glove box. The capacity of the systems for collection of effluents determines the number of successive transients that can be executed during VANESSA one BR2 cycle. In the present design, it has been set to 20 transients, back and forth. ∆P www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 RODEO Fig.b: MCNP model of RODEO, RODEO (ROtatable Device for the Execution of Operation transients) uses the strong flux gradient across a peripheral 200 mm channel to perform transients. A PWC device is inserted in a rotatable plug mounted on top of a 200 mm channel. This kind of channel is filled with a Beryllium plug fitted with 3 holes of 84 mm diameter. A 180° rotation allows a maximum displacement of 106 mm towards BR2 centre. Then, a 180 degree rotation of the plug allows to perform a two- or threefold increase of the linear power in PWC. As start and finish positions can be selected anywhere between the extremes, any amplitude within the two times limit can be achieved, possibly with a small angular motion. Furthermore, there is no limit on the number of transients that can be achieved during a cycle and there is no production of radioactive, hazardous or voluminuous waste. And on top of that, the device uses little sought- after irradiation positions in BR2. Fig.c: Axial linear power [W/cm] in function of the radial position of RODEO (MCN P preliminary calculations) 1400 1200 H3_0° H3_120° H3_240° 1000 800 600 400 200 0 -60 -50 -40 -30 -20 -10 0 10 20 30 40 50 60 The fig.c shows the axial power profiles obtained for three positions of PWC (taken clockwise). The fig.b shows PWC in the 240° position. Future Work VANESSA is in the detail design phase, whereas RODEO still exists as a concept and will require further preliminary studies. The combination of both concepts in one single device is under consideration. Main Contact Person Philippe Benoit, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 IRRADIATION OF STEEL IN PBBI Background T91 ferritic-martensitic steel is a candidate material for the structures and fuel cladding of future ADS reactors. Its behaviour under the combined effects of irradiation and contact with ADS coolant has still to be assessed, in particular the corrosion behaviour. Objectives In the frame of IP-EUROTRANS / DEMETRA project, SCK•CEN proposed to irradiate metallurgical samples under PbBi. Additional samples under water or inert gas allow to discriminate the effect of the irradiation from the effect of PbBi. The programme is called ASTIR (Ads Steel T91 IRradiation).Two different irradiations are to be performed at 300°C and 450°C, up to a fluence of 2 and 5 dpa. Principal results The 300°C irradiation will be performed in CALLISTO. The samples are tensile and CT specimens. They are inserted in closed tubes if they are irradiated under PbBi and in open tubes (like it was made for CHIVAS) if they are not irradiated under PbBi. Two different PbBi chemistries are to be tested: O2-poor and O2- saturated. This experiment is therefore called TWIN-ASTIR. SPEED ASTIR Capsule & samples layout IPS outer tube CT specimen Creep tubes Support structure Capsule inner tube Wrapping foil Wrapped CT specimens (for isolation from PbBi) Not to scale The IPS2 of CALLISTO gives 0,25 dpa per cyle, or 1,25 dpa/year At 450°C, a newly built capsule is inserted in a 6-plates (standard, thus) BR2 fuel element. The samples are here CT specimens and mini tubes to test the creep behaviour of the materials. The heating of the capsule is performed by the strong gamma heating generated in the materials whereas the temperature control is performed by the thin gap of the double-walled capsule. A fuel element irradiation would give 2,5 to 3 dpa/year. As the dose accumulation rate is doubled compared to the irrradiation performed at 300°C, the experiment was given the name SPEED-ASTIR. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Future developments TWIN-ASTIR and SPEED-ASTIR got the first phase approval by the CEE (Committee for Examination of Experiments) and are in the detail design phase. Irradiation start is foreseen in cycle 5/2005 for TWIN-ASTIR and cycle 1-2006 for SPEED-ASTIR. Main contact person Philippe Benoit, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 IN-PILE INSTRUMENTATION DEVELOPMENT Background Advanced irradiations in research reactors require the on-line monitoring of crucial parameters like neutron fluxes, gamma dose rates, central fuel rod temperatures, fission gas release pressures and small geometry changes. Our activities in this field aim at a detailed understanding of the sensor behaviour in the irradiation conditions in order to extract reliable real-time information. Objectives study of the on-line in-pile measurement of gamma and neutron fluxes in real time; study of parasitic radiation-induced signals in instrumentation cables. Principal results 1. SMFC (Sub-Miniaturised Fission Chamber) testing and performance analysis The FICTIONS programme aims at testing new SMFCs for the in-core detection of thermal and fast neutron fluxes. In collaboration with CEA/Cadarache, who is developing the SMFCs, we tested two 235U SMFCs for thermal neutron flux measurement in PWR conditions up to a neutron fluence of 5.4·1020 n/cm². The SMFC behaviour was tested as a function of irradiation temperature, of the chemistry of the surrounding water and of the accumulated neutron fluence. As a preparation for the testing of newly developed 242Pu SMFCs for fast neutron detection scheduled for 2005, the thermal behaviour of a set-up with a B4C thermal neutron screen was studied in a short irradiation test. In accordance with model calculations, the modified design ensures an efficient evacuation of the significant heat produced by neutron capture in the B4C. Central part of the test set-up for studying the thermal behaviour of an optimized B4C thermal neutron screen configuration (FICTIONS): from design (3D drawing) to reality (photograph) 1.01 1 t en rr 0.99 cu d e 0.98 Temperature dependence of the relative z i l FC1 a currents in fission chambers and in a 0.97 FC2 rhodium SPND: data observed during BR2 rm model FC1-2 o n 0.96 SPND1 cycle 02/2004A (FICTIONS-3) and ab initio model SPND1 data based on MCNP calculations. 0.95 245 250 255 260 265 270 275 280 285 290 temperature (°C) www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 1E-12 FC1 9.5E-13 model FC1 9E-13 ) FC2 s 8.5E-13 ² model FC2 m 8E-13 c A 7.5E-13 (µ th 7E-13 φ / 6.5E-13 FC I 6E-13 5.5E-13 5E-13 0 1E+20 2E+20 3E+20 4E+20 5E+20 6E+20 thermal neutron fluence (n/cm²) Long term evolution over five BR2 cycles (with varying BR2 power, BR2 configuration and fission chamber temperature) of the fission chamber sensitivities (= current per thermal neutron flux unit) as deduced from recorded fission chamber and SPND currents, including the expected exponential decrease curves based on the calculated effective 235U neutron interaction cross section. 2. Wide-range in-core fission chamber testing A collaboration contract has been signed with CEA-Saclay-DETECS for the irradiation test of fission chambers of type CFUR64 in CALLISTO. These fission chambers and their associated electronics provide the possibility of thermal neutron flux measurements over a very large range due to the use of multiple modes. Our main interest lies in the possible application of the fluctuation mode in fast neutron flux measurements in order to reduce the gamma-induced signal. 3. Consulting contract DEMOKRITOS (Greece) During the first semester of 2004 a DEMOKRITOS trainee was initiated in various aspects of reactor experiment design, fabrication and management. As a follow-up, a consulting contract was signed with DEMOKRITOS involving assistance in the development of a reliable in-core gamma heating measurement system for the GRR-1 reactor. 4. In-pile LVDT (Linear Variable Differential Transformer) application After previous assessment of the behaviour of Halden-type LVDTs in BR2 conditions, such LVDTs were incorporated in the OMICO rig for the on-line measurement of fission gas release. We implemented a signal interpretation algorithm based on the Halden calibration of the sensors and on the BR2 test experience. 5. Radiation-induced Electromotive Force effects in MI (mineral-insulated) cables Recorded radiation-induced currents during irradiation tests of MI cables with copper and stainless steel cores have been analysed and compared with data from coil irradiations in JMTR. A next-step MI cable irradiation focussing on effects of thermo-electric origin was prepared. Future developments • study of on-line fast neutron flux measurements by dedicated SMFCs (with CEA-Cadarache); • in-pile measurements on test fuel rods (centre-line temperature, geometry changes…). Main contact person Ludo Vermeeren, [email protected] Main references M. Wéber, I. Wéber, “FICTIONS-IV - mesure en-pile de la température au centre d’une capsule de carbure de bore: analyse des résultats”, SCK•CEN-R-3958, August 2004 L. Vermeeren, “Experimental study of radiation-induced currents in copper and stainless steel core mineral- insulated cables in the BR2 research reactor”, 23rd Symposium on Fusion Technology (SOFT), Venice (Italy), September 20-24, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 NEUTRONIC MODELLING IN SUPPORT OF THE Irradiation Programmes Background Irradiation experiments are generally conducted to determine some specific characteristics of the concerned fuels and structural materials under well defined irradiation conditions. For the determination of the latter the BR2 division has an autonomous reactor physics cell and has implemented the required computational tools. The major tool used is a three-dimensional full-scale Monte Carlo model of the BR2 reactor developed under MCNP- 4C for the simulation of irradiation conditions. Objectives to evaluate and adjust previsonnal irradiation conditions by adjustments of the environment, differential rod positions, axial and azimuthal positioning of the samples, global power level, ...; to deliver reliable, well defined irradiation condition and fluence data during and after irradiation; to assist the designer of new irradiation devices by simulations and neutronic optimisations of design options; to provide computational support to related projects as a way to valorise the capabilities that the BR2 reactor can offer. Principal results The major evaluations conducted during 2004 are: Ongoing Irradiation Programs: OMICO: calculation of the power distribution in the experimental MOX fuel rods to allow for online absolute LHGR measurements. UMo MTR fuel development: recalculation of the irradiation history of various fuel plates in the dedicated FUTURE irradiation device; determination of detailed burn-up distributions; comparison with the results of the latest dosimetrical measurements. U3Si2 MTR fuel qualification at high heat fluxes: preparation and follow-up of an irradiation programme of advanced MTR fuel U3Si2 fuel plates inserted as the outer ring in a 6NG standard BR2 fuel element. optimization of the Mo-99 production yields in the PRF-type devices for various target geometries and loading schemes. Modelling of newly proposed irradiation devices: this figure The right this figure shows the modelling of a carousel-type illustrates the modelling of a proposed device for power rotating irradiation facility located in the reactor pool ramping on single fuel pins using various rotating absorber outside of the BR2 vessel for Si-doping production screens. The figure gives a cross section of the BR2 core at activities. +30 cm above the mid-plane. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 On the left the MCNP calculation model of the tokamak On the right the calculated neutron spectra in different parts building of ITER. This model has been used for the of the tokamak of ITER evaluation of the activation of the biological shield. New Irradiation Devices: the GRIFFON project: neutronic optimisation of a pool-side facility for the irradiation of RVS samples under very demanding conditions (temperature range, dose rate, fluence homogeneity). This optimisation also concerned cooling and shielding evaluations. neutronic evaluations (available fluxes, spectra, deposited power, gamma heating) of various proposals for a pool-side facility for Si-doping of large ingots. neutronic evaluations of various proposals for the realisation of power ramps on fuel pins (e.g. rotating solid screens, asymmetrically loaded rotating devices, variable concentration of absorbing materials in the cooling water). Optimisation of irradiation devices containing Pb-Bi. BR2 specific evaluations: detailed heat flux distributions in the standard BR2 fuel elements in function of the BR2 configuration and the burn-up in the fuel plates; evaluation of uncertainty factors. optimization of the BR2 fuel cycle using burnable absorbers (e.g. Cd-wires in the side-plates). Evaluations in support of other projects: - determination of the effective cross-sections for dosimetrical evaluations. - Fusion: activation of the concrete in the biological shield in the present ITER design. Future developments For 2005 a number of evaluations in the framework of the 2006 decennial safety reassessment of the BR2 reactor will have to be performed. This will mainly concern detailed evaluations on the poisoning of the beryllium matrix in function of various operation schemes and a detailed evaluation of the distribution of the fluences of the walls of the aluminium pressure vessel. Fast flux booster: increasing the fast flux in samples located in the axis of standard BR2 fuel elements by geometrical or material modifications of the inner plates of the fuel element or by introducing some fissile material close to the samples. Further follow-up of the OMICO-MIMAS-PV irradiation programme. Further investigation for the BR2-RJH-U3Si2 irradiation programme, including detailed Determination of the burn-up distribution. Main contact person Edgar Koonen: [email protected] Main reference V.Kuzminov, M.Wéber, E.Koonen, "Determination of the Linear Power in MOX Fuel Rods Irradiated at the BR2 Reactor", PHYSOR-2007, Chicago, April 25-29, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 NUCLEAR RESEARCH AND SOCIETY Gilbert Eggermont Scientific Staff: Gunter Bombaerts, Michel Bovy, Benny Carlé, Pascal Deboodt, Chloée Degros, Gilbert Eggermont, Isabelle Fucks, Paul Govaerts, Frank Hardeman, Erik Laes, Steven Lierman, Mark Loos, Gaston Meskens, Bernard Neerdael, Ludo Veuchelen, Geert Volckaert Supporting Staff: Véronique Mertens, Catherine Spect, Dominique Trépagne-Glinne www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 SOCIAL ASPECTS IN NUCLEAR RESEARCH AND TECHNOLOGY DEVELOPMENT (PISA) Gilbert Eggermont Background SCK•CEN started five years ago the structured programme PISA with support of young researchers in social sciences from different disciplines and universities. They joined technical teams within SCK•CEN to increase our scientific insight and objectivity. PhD and post-doc projects were organised within specific research tracks mentioned below. The concept of reflection groups was more output-directed with closer university interaction. The reflection groups on Ethics and Expert Culture extended to Public Involvement operate with external experts (e.g. university professors and promoters) and interested SCK•CEN colleagues from different divisions and various levels from young researchers up to managers. The first three PhD's were defended in 2004. Moreover an evaluation was made of particular missions given to PISA such as the implementation of the ethical charter for SCK•CEN. Objectives The original objectives of the PISA programme as mentioned in earlier scientific reports are being realised. The evaluation of five year of PISA experience leads to some adjustments. In order to tackle constraints such as the lack of transdisciplinary culture in universities and the historical mistakes in the nuclear sector, work was focussed on a better insight in the interaction between the nuclear culture and society. It is the aim to apply transdisciplinary problem oriented methods in PhD's work, in contract research, in international networking and to take challenging opportunities in conferences. PISA had to reconsider its integration within the SCK•CEN structure and its cooperation with universities and international networks. Principal Results In 2004, we organised proactive meetings of reflection groups on involvement and ethical aspects of radiation protection in a different way than the years before. For public involvement, a start was given to the European research project COWAM II (Community Waste Management – Improving the Governance of Nuclear Waste Management and Disposal in Europe), not only by associating the local partnership MONA in Mol but also by associating indirectly other Belgian actors such as ONDRAF/NIRAS, and some Belgian local partnerships such as STOLA (Dessel) and PALOFF (Fleurus- Farciennes). Moreover relevant modelling of social dialogue and transparency in decision making, as it is developed in Sweden and the UK with the RISCOM model, was considered in more depth. The Belgian state of the art on involvement was summarized for the Berlin COWAM Seminar supported by EC. The consideration of progress on involvement of the public in complex technological developments outside the nuclear field, such as a consensus conference on bio-safety, was fruitful. It was further extended to industrial high level consultancy collaboration on matters as sustainability, transparency and governance. We prepared a project for EC submission (EURADGOV) on the remediation involvement regarding radium contaminated soil in Olen. This was based on the SCK•CEN inventory studies of the Radiation Protection Department, as reported in the Flemish Environmental Report (MIRA). On expert culture, a Master thesis was made at VUB (Vrije Universiteit Brussel) on the implementation of the ethical charter. It was based on a theoretical philosophical framing referring to Kant. The results will be helpful to redirect the ethical process within our Centre. They are used to recommend approaches on demand from the other research centres. The development of an ethical code for the International Association of Radiation Protection, a professional organisation, which many experts at SCK•CEN and PISA adhere to, was critically discussed, helping the Belgian Association of Radiation Protection to shape this process. A comparison was made with ethical development processes in high level institutions, such as the Art. 31 EC consultative Committee and the Belgian Health Council. An active participation was given to the analysis of precaution in health and environmental policy in the Health Council of the Netherlands, preparing a report for 2005. The particular issue of explanation of ethical choices in radiation protection was considered in depth through brainstorming of the PISA team, together with CITES (Centre de Recherche Interdisciplinaire Technique, Sciences et sociétés), UCL and the radiation protection division of SCK•CEN. A contribution was given to the consultation of the ICRP 2005 draft basic safety standards where ethical and legal issues were critically reviewed on EC demand. We started collaborations with different universities abroad (Milan, Tilburg, Stockholm). Finally the actual issue of nuclear terrorism was analysed on demand of the Academy of Medicine with support for an awareness initiative on emergency preparedness. Ethical reflections are organised for 2005 in collaboration with the VUB. It was tried to overcome the polarised nuclear phase-out discussion in Belgium through a PISA contract with the Technology Assessment Institute of the Flemish Parliament (ViWTA). A study was made on 30 years www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 nuclear controversies in Belgium. An approach on lessons learnt could contribute to a new constructive dialogue on energy policy. The PISA research was further organised in five tracks, two of them are discussed in highlighted chapters while three are summarized below 1. Sustainability and Nuclear Development (SuND project) PISA researchers participated in the ongoing FP6 COWAM2 activities and attended the annual meeting and workshops of the programme. Contributions were made in the research tracks of ‘Implementing Local Democracy’ and ‘Long Term Governance’. In the frame of the research on global decision making, researchers attended the 12th Commission on Sustainable Development of the UN and the 10th Conference of the Parties of the UN Framework Convention on Climate Change. SuND also joined a new SERF working programme (Socio-economic Research on Fusion) of the EFDA research group (European Fusion Development Agreement). Within this programme, SuND started ‘Research and guidance related to scenario and modelling exercises around fusion as a part of the energy system’ and ‘Focus group research around fusion as a part of the energy system’. In the framework of a doctoral thesis at KULeuven (Katholieke Univeristeit Leuven), papers were written on the case of the Belgian nuclear phase-out and on elements of sustainability in the Belgian electricity sector. A contribution was given to a European Delphi study on energy prospectives. Finally, with support of the Human Ecology Department of the Vrije Universiteit Brussel (VUB – Free University of Brussels), PISA performed an historical analysis of the societal debate on nuclear energy in Belgium. SuND expertise on unstructured energy problem discussions and TA were valorised into this work, which will be edited in a book to be published by ViWTA. 2. Transgenerational ethics and group think in nuclear waste management A master thesis was made at the Philosophy Unit of the VUB continuing earlier PISA post-doc work of promoter Prof. Dr. Gustaaf Cornelis. Principles were developed for a transgenerational ethics in the context of the ideas of John Rawls in his theory of Justice and applied to retrievability. Exchange of ideas was also organised with recent PhD work on broad transgenerational ethics at UCL (Prof. Axel Gosseries). A PhD was successfully defended at UGent on group think mechanisms in nuclear waste disposal management by Gunter Bombaerts. It is entitled "Waste depositionism, a philosophical inquiry on technoscientists and nuclear waste". His new philosophical theory, resituating risk assessment in context developments, is illustrated for small group decision-making in nuclear waste local partnerships, leading to contextual dissonance reduction. This is discussed in more details in a highlight below. PISA took up the Belgian Coordination in the European project COWAM II. 3. Legal aspects and liability The most important achievement of the legal research team was the successful public defence of the PhD of Steven Lierman entitled: “A legal analysis of the use of ionising radiation in medical hospital practice: an inquiry into the influence of prevention and precaution on health protection and liability”. It was presented in more details in the Scientific Report 2003 . The PhD thesis was published in a book edited by Intersentia, Antwerp-Oxford and was awarded the biannual André PRIMS Price. The main positions taken on precaution in particular were challenged during a workshop in Mol, which proceedings are in progress. PhD research was continued with UCL (Université Catholique de Louvain, Louvain-la-Neuve) on nuclear safety regulation, in particular its enforcement. This work involved an analysis of the international, European and national legal instruments supporting the nuclear safety standards. The many faces of soft law appearing in this frame raise the question of their interaction with liabilities and sanctions for an effective nuclear safety. The research especially takes into account the recent trends in the regulation of technological risk and environmental protection. Contacts with regulatory bodies and with industry were established in view of achieving a clear picture of this regulation in Belgium and the EU. PISA was invited to act on the UPEM conference in Copenhagen: “Uncertainty and Precaution in Environmental Management”, June 7-9, 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 4. Risk management The research about Safety Culture in collaboration with the Ulg (University of Liège) has lead to a successful Ph.D. thesis defended by Isabelle Fucks. Her work in this field of research was original in several aspects. First of all, the methodologies used (observation and 'focus groups') including direct input from the work floor and stimulating a free expression of ideas, were innovative in this field of research. Second, she paid a lot of attention to informal aspects of the safety culture. Some examples are the situations enhancing or hindering group building at all levels in the hierarchy, the informal contacts and appreciations, the so-called 'savoir- faire' (skills) of the workforce, etc. A safety culture exists even without explicit initiatives by the management. Moreover different subcultures were distinguished. She showed that improving safety culture requires a bottom-up input, which is more stringent than a top-down approach. Moreover, a formal commitment of management, including a system for follow-up and evaluation was indicated. This viewpoint is partly complementary, partly opposing the formal approach preached by international organisations such as the IAEA. The other research initiatives within the Radiation Protection division are related to stakeholder involvement and risk perception. These studies are situated in the context of the sitting of a low level radioactive waste repository in Mol (multi-criteria analysis) and in the participation of stakeholders in the context of agricultural countermeasures, in case of a radioactive contamination. They are detailed as highlights of the Decision Strategy Research Department in this report. Finally a collaboration was given to the steering committee of Science and Precaution Interactive Risk Evaluation (SPIRE), studying the implementation of the precaution principle in policy making on health and environment at work, where, after a case study on ionising radiation (radiology) in the Health Council, some contributions were given to a Delphi study by STEM (Studiecentrum Technologie en Milieu of the Universiteit Antwerpen - University of Antwerp) together with FTU (Fondation Travail-Université Namur). 5. Ethical challenges This work is highlighted separately as "Social justification of risks, an ethical challenge". Future developments The PISA programme could be reconsidered within the strategic planning of SCK•CEN and more particularly focussed on sustainable development related to energy such as crisis management. This includes precaution; ethico-legal issues and involvement. The PISA team is going to be more integrated as a unit within the more matrix oriented structure of the research centre. Alongside continuous research with regard to transdisciplinary aspects of technology assessment and global decision making, research will continue within the above mentioned COWAM2 and SERF programmes. A doctoral thesis entitled ‘Reconciling sustainable development and nuclear energy? Theoretical reflections and critical-interpretative research towards a better support for decision making.’ will be completed in the spring of 2005, followed by a reflexion group discussion at KUL or at SCK•CEN in Mol. Work on risk management will focus on crisis management, perception and precaution, while reflection groups will be organised in VUB on nuclear terrorism and ethics, continuing earlier initiatives on non- proliferation and on medical awareness for terrorism. Reflexion meetings are being prepared at UGent and ULg discussing with Belgian and international stakeholders the results of the two recent PhD's respectively on positionism and on safety culture. At UCL, a reflection meeting is planned on transgenerational ethics in nuclear waste and a conference on ethical and legal issues regarding new developments in ICRP Basic Safety Standards. Particular attention will be given to on justification and optimisation in the context of responsibility, precaution and soft law (ALARA principle) with development of new PhD proposals. Main contact person: Gilbert Eggermont, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 SOCIAL JUSTIFICATION OF RISKS, AN ETHICAL CHALLENGE Background The expert culture needs more ethical reflexion in a risk based society. In order to improve transparency goals in a more democratic decision-making process, the contributions of several types of expertise must be gathered in a trans-disciplinary approach. In Belgium, the involvement of the population in the nuclear waste management projects at local level (Mona and Stola) is seen as a positive support for building social consensus and as a main channel for communication with laymen. At global level, the role of experts in the editing of safety standard and radiation protection guidance stresses the importance of giving more attention to peer review both from scientific side as from society interests. Within European decommissioning policy we see clear needs for comparisons and justification, especially in fund management on the long term. This could help the population to fill the gap between complex issues and legitimated demands for information. Questioning the mandate of experts and reviewing their contribution will help making explicit basic issues that deal with more social concern for future cost of energy, environmental protection and possible scenarios of energy supply. The governance approach addressed to future generations asks for more social justification from scientists, experts and politicians. This requires specific efforts to build up sustainable platforms of dialogue on controversial topics. Objectives Support ethical considerations in different reflexion groups; Enhance transparency within the communication processes; Favour social review in decision-making processes dealing with expert culture analyses; Suggest more involvement to improve democratic attitudes in techno-scientific reflexion. Principal results Equity as a philosophical argument in making explicit social values in the "Justification principle" in radiation protection has been integrated in 2004 in several reflexion groups, both on Belgian side (SCK•CEN, UCL, Fondation Roi Baudouin, Belgian Association of Radiation Protection, ULG) and at international level (reflexion groups and colloquia at ICRP, IRPA, OECD and research networks such as COWAM). The role of experts within Art. 31 of the Euratom Treaty is made more explicit and some first comparisons were initiated with the company culture at SCK•CEN. We helped elaborating brainstorming among experts on ethical concepts of ICRP recommendations and gave some ethical support for a critical review on demand of RISSH for the Art. 31 expert group of EU. Innovative sociological approaches of B. Latour have been integrated into the PhD research (on Nuclear Waste depositionism) to favour the role of stakeholders in decision-making and to enlighten the interactions between experts and society in the definition and use of safety concepts. Future developments Research in ethics and the integration of precaution approach, inter-generational ethics for future generations (decommissioning project, waste management), will be further developed. The Cowam II network and its related research collaboration will generate reports and exchanges of experience. International contributions are prepared on the expert culture in fund management with regard to the decommissioning project. Some additional contributions are planned in the EFDA program research on fusion (focus groups) in the SERF area (Socio Economic Research in Fusion). Main contact person Michel Bovy, [email protected] References M. Bovy, Ethics and funds: an inter-generational equity decided by intra-generational equity, Working Party on Decommissioning and Dismantling Radioactive Waste, Management Committee OECD/NEA, 26 pages, Paris, Meeting 8-10 November 2004. G. Eggermont., M. Bovy, B. Feltz and P. Smeesters, Ethical and Legal Issues, Criticalreview of ethical and legal issues, in the draft 2005 Internal Commission of Radiation Protection (ICRP) Recommendations, EC- DG TREN - Workshop Art. 31 EURATOM, Group of Experts, Luxemburg 4/11/2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 TOWARDS A NEW UNDERSTANDING OF TECHNOLOGICAL DECISION-MAKING Background The safety assurance of technological developments is becoming one of the most important tasks of technology. The limitation and the fallibility of technology are core issues in the attempt to guarantee safety. It often happens that scientific facts, both in general and safety facts in particular, are refuted and revised. This demonstrates that science can learn from its mistakes. It also puts forward the question of the status of scientific facts. How is it possible that 'incorrect' scientific facts could in some instances convince almost an entire scientific community in the past? Are the facts these days waiting for the same fate tomorrow? For nuclear waste repositories and their surroundings, it is important to know what will remain from current safety assessments within a few hundred years. This brings us to the core of our transdisciplinary research: which meaning can we attribute to the safety assessments of scientists and technologists? Objectives To describe how facts are determined within small groups during a decision-making process. And as a consequence hereof: To show why scientists and technologists accept or refute these facts. The general objectives are applied to safety facts in radioactive waste management. Principal Results The principal results are threefold: a philosophical model and two empirical illustrations hereof. A philosophical model First of all, a new philosophical model has been elaborated entitled 'positionism'. The start point is that statements are facts for a network if they are not questioned within this network. Such a network consists not only of people but also of objects (79Se half-life example below). If an object acts differently from what a theory predicts, this theory is not considered as a fact. Positionism builds on this point of view to explain how facts take form in a sequence of contexts. A context is a problem-solving situation in which individuals work out a problem framing and use their attitudes (affects, behaviour and cognitions), their personalities, the existing group cultures, and relevant objects that are present. Such a context is very limited in time and with respect to the context elements that are explicitly present. However, a context has many implicit links between the explicit context elements and other elements. These links give to the context elements their contextual strength. The theory describes the solution of the problem as a contextual dissonance reduction. If the problem is formulated, two context elements or clusters of context elements will be dissonant. The context actors will be motivated to reduce this dissonance. The direction in which this dissonance takes place will however depend on the strength of the present context elements. This means that no predefined ontology is possible. Let us give an example. Recently, the half-life of 79Se has been changed from 6,5 104y to 1,1 106 y. Suppose some technoscientists discuss the safety of a radioactive waste repository. In the decision-making process on the safety, an inventory is made of the different isotopes. Suppose 79Se is one of them and at a certain moment, some technoscientists reconsider its half-life. Some say that 79Se's half-life is 6,5 104y according to the catalogue present in the room. Others say that they have read a report – which they do not have with them - of Vienno and Nordman, stating that the most probable half-life is now 1,1 106 y. The elements are dissonant and the way this dissonance will be solved depends on the strength of the present context elements. How are Vienno and Nordman perceived? Is the group willing to review its own cognitions? Etc. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 79 4 79 4 79 6 t1/2( Se)=6,5 10 y t1/2( Se)=6,5 10 y ↔ t1/2( Se)=1,1 10 y 79 6 t1/2( Se)=1,1 10 y Catalogue ↔ Vienno and Nordman Technoscientist a,b,... ↔ Technoscientist x,y,… Technoscientists Half-life 79Se? Open culture Catalogue Figure 1: (a) Example of context elements (clockwise starting from above) attitude, problem framing, objects, group culture and individuals. (b) Dissonant context elements Quantitative study: Questionnaire A questionnaire has been sent out internationally asking for assessments by technologists and scientists of the risks of a high level waste repository on the one hand and their personality, group culture and background characteristics on the other hand. Two important indicators occur. High neuroticism - a personality measure indicating the general tendency to experience negative affects such as fear, sadness, or distrust - correlates with a high estimation of the waste repository risks. Scientists with high confidence in science give a significant lower estimation of the repository risks. These results illustrate in a qualitative way the contextual point of view of the philosophical theory. Qualitative study: case study Observations of the Belgian low level waste decision-making process have been made over a period of four years. These observations do not give an historical construction of the process, but are used as an illustration of positionism mechanisms. They show that certain argumentations on technology are positioned above others because of contextual aspects. These results illustrate in a qualitative way the positionism theory and its actual applications. Main contact person Gunter Bombaerts, [email protected] Main references G. Bombaerts, "Conformity and internalisation in a participative decision making process", In: VALDOR 2003, proceedings of Symposium in VALues in Decisions On Risk proceedings, Ed. Kjell Anderson, Stockholm, 2003, 336-344 G. Bombaerts, "Value judgement in Risk Analysis", In: G. Eggermont, Mark Coeckelbergh and Anne Verledens (eds.)., Ethical choices in Radiation Protection – in Search of Precaution, SCK•CEN BLG-936, 2003, 23-26. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 MANAGING NUCLEAR KNOWLEDGE Scientific Staff Raf Aarts, Abderrahim Al Mazouzi, Hamid Ait Abderrahim, Philippe Antoine, Baudouin Ariën, Sarah Baatout, Peter Baeten, Francis Berghmans, Benoît Brichard, Paul Borgermans, Michel Bruggeman, Benny Carlé, Francis Chody, Michèle Coeck, Bernard Coupé, Jérôme Dadoumont, Pascal Deboodt, Pierre De Cannière, Yves Demeulemeester, Peter De Regge, Alberto Fernandez Fernandez, Freddy Geenen, Jean-Louis Genicot, Paul Govaerts, Mireille Gysemans, Frank Hardeman, Luc Holmstock, Christian Hurtgen, Frank Joppen, Christian Legrain, Enrico Lucon, Koonen Edgar, Isabelle Majkowski, Eduard Malambu, Lorenzo Malerba, Vincent Massaut, Gaston Meskens, Frans Moons, Luc Noynaert, Mathieu Ponnet, Bernard Ponsaert, Carlos Rojas Palma, Marie-Laure Ruyssen, Leo Sannen, Marc Scibetta, Steven Simons, Alain Sneyers, Alain Sohier, Dirk Van Beckhoven, Sven Van den Berghe, Steven Van Dyck, Filip Vanhavere, Hans Vanmarcke, Ingrid Vanregenmortel, Katrien Van Tichelen, Bernard Verboomen, Anne Verledens, Fernand Vermeersch, Freddy Verrezen, Marc Verwerft, Eric Van Walle, Marcel Wéber. Supporting Staff Monique Alen, Mario Bens, René Bubbe, Kristof Coomans, Tom Couwberghs, Hendrik De Soete, Wendy Machiels, Hans Melis, Henri-Rose Meynen, Kris Pennemans, Caroline Poortmans, Jan Ruts, Frans Slegers, Catherine Spect, Cindy Verachtert, Nancy Van der Borgt, Monique Van Geel, Els Van Musscher, Viviane Van Springel, Vera Verstraelen, Gilbert Werelds, Roger Weytjens. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 MANAGING NUCLEAR KNOWLEDGE A CHALLENGE FOR SCK•CEN Marie-Laure Ruyssen All innovation in nuclear science and nuclear technology for either power or non-power applications relies on knowledge. Preserving and enhancing nuclear knowledge accumulated in the past has become a timely subject of strategic importance. In recent years, political, economical and societal trends urged the need for an efficient management of nuclear knowledge. Foremost, the Belgian government has decided to phase-out nuclear power plants. Privatisation and deregulation rules of the energy market in the European Union drives the nuclear industry to compete in the immediate and near term with other sources of electrical energy. This might result in a reduction of work force and budgets allocated to R&D. These two decisions have as a side effect that fewer young people are attracted by studying nuclear science and nuclear engineering, making the issue of the replacement of the aging nuclear workforce even worse. This changing environment requires therefore the pro-active retention and preservation of our comprehensive nuclear knowledge base and the sustainment of our nuclear education and training efforts. 1. Preserving and sharing Nuclear Knowledge Managing the Knowledge capital is a long term journey, which started from a strategic commitment, integrating various operational projects. Since 2002, several pilot projects in different areas of expertise have been conducted to set up nuclear knowledge repositories and to sustain interactive research communities. As trust is definitively central to any knowledge sharing process, we started to gain trust by setting up a library portal. This Knowledge Centre portal was designed as a support tool in the daily work of our researchers by offering scientific information services. We integrated external high-quality scientific information sources with traditional library services. This library portal is currently evolving towards a Knowledge Management (KM) portal by enlarging its role to the management and safeguarding of the SCK•CEN Scientific Output. Beyond the establishment of a corporate knowledge sharing culture, dedicated web-based portals based on open source internet technologies ensure the long term persistence of data and the continuous capture of knowledge by providing on-line collaboration tools and related Quality Assurance procedures. In 2004 the online Waste and Disposal Community has grown for his early start-up phase to a more mature phase. Currently its portal is acting as an access point to shared document collections on topic oriented projects and task groups. Critical databases for performance assessment in the disposal of nuclear waste in the Boom clay have been set up and, state of the art reports and critical documents have been brought in and forms the starting point of in depth reviews and state-of-the-art (annotated) reports linking the major concepts and results. In collaboration with the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (NIRAS-ONDRAF), those repositories will be partially coupled to a Geographic Information System. Furthermore in 2004 we started to develop a dedicate web portal to help researchers of the Instrumentation department to handle through a graphical user interface all the scheduling and management of experiments involving the SCK•CEN gamma irradiation facilities. In the next stage we will provide a per-facility logbook. Once completed, the portal will manage all aspects of the experiment lifecycle: related documents, logbooks and storage of the raw and processed experimental data. The projects funded under the Sixth EURATOM Framework programme (FP6) present important new KM challenges for SCK•CEN. One of the aims of FP6 is to focus on the integration process of all nuclear stakeholders at European level making use of the new FP6 instruments which have a specific role in the construction of the common nuclear knowledge base. The European Commission is therefore heavily insisting on the use and dissemination of knowledge and the spreading of excellence. The mean of achieving added value through knowledge sharing and networking can be sustained through a web-based portal. Since our KM tool is based on open-source software, it can be freely distributed within a European research community as a handy collaborative and integration tool. Our KM tools also help our researchers to generate new knowledge and promote scientific excellence within new European FP6 projects: www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 In September 2004 SCK•CEN started to deploy a Knowledge Centre with the same underlying toolkit as for our internal KM projects for the Network of Excellence on Micro-Optics (NEMO). For the Network of Excellence on Actinides (ACTINET) started on March 2004, SCK•CEN brings in his experience in coordinating the KM activities of the network. As overall project coordinator of the Integrated Project in the Near Field Key Processes for Nuclear Waste Disposal (NF-PRO), SCK•CEN implements from 2004 on a web-based portal for KM, project management and training. As only a few non-profit R&D institutions have been keen adopters of the principles and practices of KM, SCK•CEN decided to bring together experts in management of scientific knowledge for a one day discourse on the 25th of March in Mol. The goal of this Topical Day was to give an up-to-date overview on how those issues are addressed in a scientific environment, to share practices between the nuclear and non-nuclear world and to support community building on this issue. This initiative was complementary to the major IAEA conference in September 2004 held in France. Furthermore IAEA invited SCK•CEN’s responsible for KM as expert for a technical meeting held in Vienna October 2004 to develop a Nuclear Knowledge Portal for the integration of existing nuclear data and information bases in the Agency and in Member States. 2. Sustaining Nuclear Education and Training In October 2004 started the third academic year of the Belgian "additional master" program in nuclear engineering (BNEN). BNEN is an interuniversity initiative of five Belgian universities and SCK•CEN. The programme extensively benefits from the staff, the research programs, the laboratories and the lodging facilities of SCK•CEN. The advanced courses of BNEN programme on Accelerators and time of flight experiments, on Decommissioning of nuclear facilities, on MOX-fuel and Severe accidents were in 2004 successfully opened to European Nuclear Engineering Network (ENEN) in order to facilitate participation of "foreign" students. This approach is based on a commonly agreed process for qualification, mutual recognition and student mobility between ENEN partners. The BNEN calendar of the third academic year is even more modularly structured to further enhance participation of foreign students and professors. Thanks to its extensive knowledge and expertise in radiological protection and radiobiology the international school for Radiological Protection (isRP) has a solid reputation in the field of training and education on all aspects of radiological protection. Besides organizing training programs for our own personnel, isRP courses are intended as well for the private sector as for the political, academic world and the general public. During 2004 -isRP organized together with the FANC and under the IAEA patronage the 'training course on the safe transport of radioactive material'. Furthermore in order to consolidate and transfer to future generations the know how of main European decommissioners, SCK•CEN co-ordinates a FP6 project called European Nuclear Decomissioning Training Facility II (EUNDETRAF II). The project creates also a forum for regular contacts to exchange information and experiences for mutual benefit of these organisations as well as to enhance the European skill base on decommissioning through a comprehensive training programme. SCK•CEN faces the challenge of handling knowledge for solving topical problems based on experience in the field, model-oriented experiments and fundamental research in domains where many experts will retire for age reasons. Our Knowledge management programme makes an essential contribution in the systematical preservation, use and transfer of knowledge not only inside SCK•CEN but also through educational networks and international training courses. Main contact person Marie-Laure Ruyssen, [email protected] Main reference M.-L. Ruyssen, F. Moons, Ch. Legrain, Managing Nuclear Knowledge: a SCK•CEN concern. Status of a practical Knowledge Management approach. Proceeding in IAEA International Conference on Nuclear Knowledge Management 2004 - Strategies, Information Management and Human Resource Development, 7-10 September 2004, Saclay, France. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 EUROPEAN NUCLEAR DECOMMISSIONING TRAINING FACILITY II Background SCK•CEN co-ordinates a project called European Nuclear Decommissioning Training Facility II (EUNDETRAF II) in the Sixth Framework Programme on Community activities in the field of research, technological development and demonstration? for the period 2002 to 2006. This was a continuation of the FP5 project EUNDETRAF. EUNDETRAF II is a consortium of main European decommissioners, such as SCK•CEN (Belgium), EWN (Energie Werke Nord, Greifswald Germany), Belgatom (Belgium), SOGIN (Società Gestione Impiantio Nucleari, Italy), Universität Hannover (Germany), RWE NUKEM (United Kingdom), DECOM Slovakia (Slovakia), CEA (Centre d'Energie Atomique, France), UKAEA (United Kingdom's Atomic Energy Agency, United Kingdom) and NRG (Nuclear Research and consultancy Group, Netherlands). Objectives The primary objective of this project is o to bring together this vast skill base and experience; o to consolidate it for easy assimilation and o to transfer to future generations by organising a comprehensive training programme. Each training course has a one-week theoretical and a one-week practical component. The theoretical part is for a broader audience and consists of lectures covering all the main aspects of a decommissioning. The practical part of the course includes site visits and desk top solutions of anticipated decommissioning problems. Due to operational constraints and safety considerations, the number of participants to this part of the course is strictly limited. The partners intend to organise altogether two two-week EUNDETRAF II training courses over a period of three years. Another goal is to disseminate the existing theory as well as the practical know-how to personnel of the third countries Finally it is important to bring together the principal decommissioning organisations undertaking various decommissioning activities. The project creates a forum for regular contacts to exchange information and experiences for mutual benefit of these organisations as well as to enhance skill base in Europe to strengthen the European position in the world. Principal results After the editing of a leaflet for promotional purposes and the writing of a textbook, the partner CEA organised the first training course of the project. The buildings of CEA in Saclay, near Paris, hosted the course from November 22 till December 03, 2004. Twenty-nine participants of 13 different countries participated in the theoretical part while fifteen participants had a practical training. The last part included a lot of visits in different French nuclear facilities amongst them the EL4 Brennilis site, the AT1 site and different decommissioning projects of radiochemical laboratories and waste sites. There was a very good feedback of the participants on both parts of the course. Participants of the first EUNDETRAF II training course held from November 22 till December 03, 2004 Future developments The second course will be organised in 2005 or 2006 in Italy by SOGIN. Next year, the discussion will start on the future of the course. Should the course become commercial or should it be a part of a larger European educational network? These are questions that have to be answered in the near future. Main contact person Yves Demeulemeester, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 EDUCATION AND TRAINING IN RADIOLOGICAL PROTECTION THE ACTIVITIES OF THE ISRP Background The International School for Radiological Protection (isRP), a task force within SCK•CEN, co-ordinates and organises training programs on all aspects of radiological protection. IsRP courses are directed as well to the private sector as to the political and academic world and the general public. Objectives International meetings, publications and recommendations with regard to safety culture increasingly stress the importance of education and training in the field of radiological protection. In addition, the need to standardise and harmonise the recognition of skills and practices on a national and European level is emerging. In this sense, the objectives of isRP are threefold : (1) to continue the organisation of open courses and training-on-demand of which the programmes are made up according to the background level and training requirements of the participants, and this for the Belgian medical and industrial sector; (2) to come to a closer cooperation with national universities and high schools and relevant international institutions; (3) to contribute to a better harmonisation of training practice and of skills recognition on a national and European level. Principal results Throughout 2004, isRP organised 14 training courses of various length and scientific level for as well national as international groups, including groups of EC DG TREN and EC EuropeAid. In January 2004, 11 participants started in the second edition of the 120h- course for the 'radiation expert', organised by SCK•CEN-isRP and Hogeschool Limburg. The programme for this course is based on the requirements as expressed in the Belgian law regarding training of the radiation expert and is considered as a one of the requisite conditions to obtain the licence of safety inspector. From June 28 to July 9 SCK•CEN-isRP, together with the FANC, organized the 'training course on the safe transport of radioactive material'. These classes, organised under the IAEA patronage, were attended by 18 persons from the middle-east and 5 from Belgium. During two weeks the participants studied the legislation on the safe transport of radioactive material. In addition to the theoretical curriculum, visits of Hades and BR3 at the SCK•CEN and of the preparation of radiopharmaceuticals for dispatch at the IRE were organized. An exercise simulating a transport accident helped the participant to learn the role of the competent authority, the fire brigade, the ambulance, the hospital, the police and radioprotection intervention team in such circumstances. On a European level, the isRP Programme Manager is coordinating the ENETRAP 6FP Project (European network on education and training in radiological protection) and participates in the EUTERP platform (European Platform for Education and Training in Radiological Protection). Both projects aim at the harmonisation of education and training on an international level. Future developments Determined to build further on what has been achieved up to now, isRP will continue developing its training courses for SCK•CEN personnel and professionals from the medical and industrial sector dealing with ionising radiation. Together with the FANC and in cooperation with the European Nuclear Society, SCK•CEN-isRP will also organise the 3rd international conference on education and training in radiological protection, ETRAP2005, in Brussels in November 2005. Special attention will be paid to the networks currently emerging at the European and global level and the conference aims to send out a declaration on the harmonisation of training practice and of skills recognition on European Level. Main contact person Michèle Coeck, [email protected] Main reference www.sckcen.be/isrp; www.etrap.net www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 OPEN ACCESS TO THE BELGIAN NUCLEAR HIGHER EDUCATION NETWORK Background Under the name of the Belgian Nuclear higher Education Network (BNEN), five Belgian universities (Katholieke Universiteit Leuven, Université Catholique de Louvain, Universiteit Gent, Université de Liège, Vrije Universiteit Brussel) have established in 2002, in collaboration with the Belgian Nuclear Research Centre SCK•CEN, a common Belgian Interuniversity Programme of the third cycle leading to the academic degree of "Master of Science in Nuclear Engineering". Under the lead of the SCK•CEN a project to use and share the acquired experience of the Consortium BNEN - in order to support the realization of a common "European Education Programme in Nuclear Engineering" – has been accepted by the European Commission for funding under the EU's Sixth Research Framework Programme. Objectives The project wants to contribute actively to the development of a more harmonised approach for education in nuclear sciences and engineering in Europe. It brings the European higher Education Area closer to realization and helps to safeguard the necessary competence and expertise for the continued safe use of nuclear energy and other uses of radiation in industry and medicine in Europe. The project foresees input and participation from stakeholders from different countries of the enlarged European Union (EU-25) and will therefore contribute to the integration of the new member states into the European Research Area and thus to the enlargement of Europe. The set-up of the project foresees an active role for female experts with the intention to reinforce the place and role of women in science. Principal Results First outcome of the project will be a complete compendium, describing the background, the objectives and achievements of the BNEN scheme. Furthermore the project will provide a set of evaluation criteria and corresponding evaluation methodologies for a self assessment and external evaluation of the BNEN scheme and BNEN education programme. Through the input and participation of EU-25 experts these evaluation criteria and methodologies might form the basis for a commonly accepted assessment instrument for the evaluation of education and training programmes all over Europe. At the end a report will combine the results from an extensive external evaluation of the BNEN scheme by EU-25 stakeholders, the conclusions of a self assessment, recommendations and suggestions how the BNEN scheme and experience can be used for the creation of the common "European Nuclear Education Programme", and in extension how the scheme can be useful for the set-up of European education programmes in general. Elements that are of particular importance to stakeholders of the new member countries and to women will also be integrated in the report. Future Developments It is the intention to use the outcome of this project to reinforce the European Nuclear Education Network (ENEN) and to bring the "European Education Programme in Nuclear Engineering" closer to realization. Main contact person Steven Simons, [email protected] Main reference Steven Simons, "Description of Work – Open Access to the Belgian Nuclear higher Education Network", 30 November 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 WP7: Project Management SCK•CEN Del. 0: Kick-off Meeting t = 3 m. t = 3 m. WP1: Compendium SCK•CEN UCL WP2: Evaluation Methodologies Del. 1: Compendium describing BNEN background, Del. 2: Report with chosen Evaluation Criteria and objectives and achievements Methodologies, supported by external EU-25 experts t = 4 m. WP3: Self Assessment Del. 3: BNEN File containing today's facts, the results of the self assessment, future goals and strategy to reach these goals, and a questionnaire ULg t = 6 m. WP4: External Evaluation Del. 4: EXT Report Stakeholder' s comments using a questionnaire based on the Evaluation Methodologies VUB Del. 5: Progress Meeting t = 2 m. WP 5: Dissemination Del. 7: Final Report including comments and recommendations from Conference KULv t = 3 m. WP 6: Final Report Del. 6: Dissemination Conference UG www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 FUSION Scientific staff Abderrahim Almazouzi, André Beeckmans, Philippe Benoit, Francis Berghmans, Gunter Bombaerts, Rik-Wouter Bosch, Michel Bovy, Johan Braet, Benoît Brichard, Aimé Bruggeman, Rachid Chaouadi, Camiel Decloedt, Frank Druyts, Guido Engelen, Ludo Eysermans, Alberto Fernandez Fernandez, Isabelle Fucks, Philippe Gouat, Andrei Goussarov, Frank Hardeman, Constant Hendrickx, Stefan Huysmans, Patrice Jacquet, Silva Kalcheva, Vadim Kuzminov, Erik Laes, Ann Leenaers, Enrico Lucon, Sabrina Lunardi, Lorenzo Malerba, Dirk Mallants, Jan Marivoet, Vincent Massaut, Milena Matijasevic, Steven Mellemans, Gaston Meskens, Valérie Moise, Johny Mols, Theo Noels, Hans Ooms, Luc Ooms, Antonio Pellettieri, Danny Penneman, Bernard Ponsard, Jean Pouders, Jean-Louis Puzzolante, Leo Sannen, Danislav Sapundjiev, Frans Schelles, Marc Scibetta, John Seghers, Steven Smets, Frans Swinnen, Dmitry Terentyev, Jef Valenberghs, Sven Van den Berghe, Sven Vanderbiesen, Steven Vandyck, Herman Van Eyck, Leo Van Houdt, Constant Van Ierschot, Marc Vankeerberghen, Wouter Van Renterghem, Marco Van Uffelen, Ludo Vermeeren, Göran Verpoucke, Marcel Wéber, Alfons Verwimp, Wim Verwimp, Frans Vos, Victor Willekens, Paul Wouters www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 FUSION: INTRODUCTION Marc Decréton FUSION CHANGES GEAR: THE CONSTRUCTION OF ITER Fusion research has been highlighted in 2004 as a future crucial contribution to the energy issue. The clear decision of Europe to go forward with the construction of ITER in Cadarache is an important political message. It should challenge the scientific and industrial community to bundle their effort in order to win the complex technological challenge at stake. ITER is the main element of the present fusion roadmap. Without being yet the electricity producing machine, it will integrate the different technologies that have been developed, and assess the control capability of a burning plasma device up to actual ignition. Together with the breeding blanket programme, the material research and the IFMIF testing facility, it will lead the way towards the foreseen demonstration power plant. Discussions are ongoing on a fast track option to provide commercial electricity production at the mid of the century. The decision on ITER construction questions the present organisation of the fusion programme in Europe. It requires specific adaptation inside each associated partner, such as SCK•CEN, to evolve from a research driven activity towards a more industrial approach, and to orient the on-going work into a real accompanying effort of the ITER initiative in the following decades. THE SCK•CEN CONTRIBUTION TO ITER The fusion contribution of SCK•CEN relies on several fusion-relevant core competences: wide capabilities in high neutron flux material testing, a well-established material research know-how, a recognised position in radiation tolerance of instrumentation, an accelerator-driven spallation-source reactor project and a leading role in decommissioning and waste disposal issues. The fusion involvement of SCK•CEN is therefore articulated around these strong poles and addresses one of the crucial issues for the fusion technological development, and ITER in particular: “What is the expected lifetime of materials and equipment under the severe radiation environment of a burning plasma environment?” We have the ability to tackle such an assessment in a very comprehensive way, taking full use of the BR2 material testing reactor, fully equipped hot-cells close by, a wide range of gamma facilities and specialised laboratories capable to handle tritiated materials and toxic metals such as beryllium. Our specificity is recognised by the international co-ordination role we assume on the performance of new steels under radiation, and the radiation hardening of instrumentation. ITER plasma facing materials The first wall of ITER will be made of beryllium. Taking advantage of the availability of highly irradiated beryllium from the BR2 matrix, post-irradiation examinations are conducted to study the combined effect of radiation and high temperature on the material swelling, creep characteristics and helium release. In collaboration with FZK (Karlsruhe, Germany), this allows to validate a radiation effect modelisation of this material. The reactivity of beryllium in contact with steam is also studied as a contribution to the safety analysis of ITER. In 2004, a new beryllium alloy was particularly studied capable to reduce the production of hydrogen in case of a loss of coolant accident (See the contribution on "Chemical Reactivity of Titanium Beryllide in Air" in this report). In collaboration with FZJ (Jülich, Germany), a study has been launched on the behaviour of different first wall metals (beryllium, tungsten and carbon) under radiation and thermal shocks (See the description of this work in the contribution on "PhD Candidates and Postdoctoral Researchers: Selection 2004" in this report). This is of particular importance to guarantee the integrity of the first wall in the event of plasma disturbances, such as edge localised modes for instance. The cooling blanket of ITER The cooling of the first wall will be insured by a circulation of pressurised water in cooling blanket modules. The copper ducts in the blanket will be subject to radiation, corrosion and high stresses. A unique in-situ irradiation device developed in collaboration with VTT (Finland) allows analysing in BR2 the combined effect of neutron bombardment and mechanical stresses in copper alloys, approaching so more closely the actual conditions of the material inside the blanket (See the contribution on "Irradiation of fusion materials" in this report). The copper-steel joints form a delicate part of the assembly. Such joints are being assessed under a representative neutron fluence to guarantee their reliability during ITER lifetime. Moreover, behind the blanket modules, attachment parts in titanium and inconel are also subject to a severe environment. Irradiation tests have been conducted on titanium and microstructural analysis of irradiated inconel bolts are planned. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 The ITER breeding test blanket module ITER will be used to test the future breeding concept to be used in a power plant. A breeding test blanket module is being developed based on helium cooling and a pebble bed approach of lithium silicates and beryllium pebbles, inside a structure made of low activation (Eurofer) ferritic martensitic steel. An alternative concept is also under study, involving a liquid lithium-lead breeder. The new Eurofer steel is subject to an extensive assessment under representative radiation conditions in the BR2 reactor. Its mechanical characterisation after a fluence corresponding to the complete ITER operation time is being performed, together with the corrosion resistance to liquid metal. As the present experiments do not involve 14 MeV fusion neutrons, modelisation work is needed to extrapolate the results to the real ITER conditions. The new steel is therefore modelled by a binary alloy Fe-Cr for which a multiscale modelisation approach is applied for the radiation effects, ranging from atomic simulation to macroscopic property prediction (See the contribution on "In-cascade clustering in Fe-Cr alloys" in this report). Moreover, the higher helium production typical of high energy neutron bombardment is simulated in experiments where pre-implanted helium specimens are used. In collaboration with IBA, we also evaluate the design of the future 14 Mev neutron material testing facility, IFMIF, and in particular its accelerator systems. Plasma diagnostics for ITER Diagnostics systems have been developed on existing tokamaks where no radiation constraints are present. ITER sets a particular challenge to these developments by requiring a high radiation tolerance in a severe environment. SCK•CEN has focused its work on optical fibres, in order to allow for more flexible optical diagnostics. In particular the efficiency of hydrogen treatment as a hardening technique has been studied and validated in JET during the recent deuterium-tritium campaign (See the contribution on "Optical fibres for fusion plasma diagnostics systems" in this report). The degradation of insulation materials used in several diagnostic systems, and in particular the radiation induced parasitic effects appearing in mineral insulated cables has been experimentally and theoretically analysed, in order to provide a sound basis for the design of the ITER systems (See the contributions on "Fusion ceramic materials and components" and on "In-pile instrumentation development" in this report). Remote handling instrumentation for the maintenance of ITER Fusion machines require a more demanding remote handling for their maintenance than fission reactors. The successful in-vessel remote maintenance operations at JET have shown the technological maturity of this approach. But its extrapolation to ITER will require a substantially higher radiation hardening of all sensing systems embarked on the handling units. SCK•CEN coordinates the European efforts in this domain and maintains the European database of the related radiation tolerance information. We set also particular emphasis on optical multiplexing techniques to alleviate umbilical problems of the handling units (See the contribution on "Communication links for fusion reactor maintenance operations" in this report). In collaboration with the industry (particularly the Gradel company in Luxemburg), complex mechanical components are designed and manufactured for the remote handling prototype machines. ITER waste management and public acceptability of fusion energy The fusion option is particularly attractive for its waste characteristics, in particular for making deep geological disposal unnecessary. ITER would be a good test case to validate the needed waste strategy. Particular problems are for instance still to be solved, in order to detritiate the generated waste and to cope with toxic metals such as beryllium. SCK•CEN helps for instance optimising specific detritiation techniques in collaboration with FZK (See the contribution on "Water detritiation: better catalysts for liquid phase catalytic exchange" in this report), and studies waste strategy issues such as recycling (See the contribution on "Recycling fusion materials" in this report), disposal criteria and conditioning performance. The waste problem touches a sensitive aspect of energy production: its acceptation by the public. Socio- economics aspects are therefore important in this debate, and must be considered with great attention. As part of its social science programme, SCK•CEN is evaluating communication aspects with the public. In particular, the public opinion around Cadarache as potential ITER site was analysed via focus groups, and this study is now extended to a larger basis. Contact Marc Decréton, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 CHEMICAL REACTIVITY OF TITANIUM BERYLLIDE IN AIR Background Beryllium is the current reference neutron multiplier material is most breeding blanket concepts for DEMO, the demonstration fusion reactor to be build after ITER (the International Thermonuclear Experimental Reactor). Indeed, beryllium offers favourable neutron multiplying properties due to the reaction 9Be (n,2n) 2 4He. There are however safety hazards associated with the use of beryllium, in particular its highly exothermal reaction with air and steam at high temperatures. Therefore, recent R&D focused on the development of alternative materials for pure beryllium. At SCK•CEN, we investigated the effect of ion implantation in the beryllium oxide layer on chemical reactivity. JAERI, on the other hand, developed intermetallic beryllium compounds, with Be12Ti being the most advanced at the moment. This titanium beryllide is reported to offer lower chemical reactivity, a higher melting point, and lower helium swelling under neutron irradiation in comparison with pure beryllium Objectives To assess the chemical reactivity in air (and steam) of Be12Ti (Be-7%Ti) at temperatures relevant for the HCPB (Helium Cooled Pebble Bed) breeding blanket (450-900°C). Principal results We used TGA (thermogravimetric analysis) to determine the reactivity of Be12Ti in air. We calculated the average oxidation rate based on the total mass increase during the experiment and the initial surface area of the sample and compared this with the reaction rate for commercial pure beryllium. The figure below shows the average oxidation rate as a function of temperature for both Be12Ti and unalloyed beryllium. The reaction rate of the beryllide is lower than that of beryllium by a factor 4-6 in the temperature range 450-800°C. At 900°C, the difference increases to a factor 20. Temperature [°C] 900 800 700 600 500 10-2 x Be Ti 12 + Be s] . ² m -3 / 10 g [ e t a n r io at 10-4 oxid e ag r e v A 10-5 8 9 10 11 12 13 14 Inverse temperature [10000/K] Overview of chemical reactivity results: average beryllium oxidation rates for Be12Ti (x) and unalloyed beryllium (+) as a function of temperature. The average reaction rates are based on the geometric surface area and on the total mass gain after 21400 s of exposure to air at the indicated temperature. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 4,0 80 3,5 ] ²] 3,0 ² 60 /m /m [g 2,5 [g n n i i a a g g s 2,0 s ss 40 a a M 1,5 m 1,0 20 0,5 0,0 0 0 5000 10000 15000 20000 25000 0 5000 10000 15000 20000 25000 Elapsed time [s] Elapsed time [s] TG-curve for Be-7%Ti exposed to air at TG-curve for beryllium exposed to air at 900°C. 900°C. The figures above show the individual TGA curves for the two materials at 900°C. The shape of these curves yields information about the oxidation mechanism of the metal. At lower temperatures, the oxidation kinetics is parabolic for both materials. This indicates the growth of a protective, coherent oxide layer. At 900°C, the two materials behave in a different manner. For beryllide (left figure) the kinetics is still parabolic and the oxidation protective. In the case of unalloyed beryllium however (right figure), the reaction rate increases as a function of time. This type of TGA curve is associated with breakaway of the oxide layer. Oxidation continues until the metallic beryllium is depleted. The obtained results confirm that the oxidation rate of titanium beryllide is lower than the oxidation rate of unalloyed beryllium, but the effect is rather low at temperatures up to 800°C. The advantage of the beryllide is that no breakaway occurs at temperatures up to at least 900°C. Future developments The next phase of the research plan foresees tests in steam. We will also extend the investigated temperature range up to 1000°C to verify if breakaway occurs for the beryllide material at this temperature. Main contact person Frank Druyts, [email protected] Main reference F. Druyts, “Interaction of Be12Ti with air and steam at HCPB BB relevant temperatures – Interim report on the results in air,” SCK•CEN contract report R-4038, October 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 RECYCLING FUSION MATERIALS Background The inherent safety and environmental advantages of fusion power in comparison with other energy sources play an important role in the public acceptance. No waste burden for future generations is therefore one of the main arguments to decide for fusion power. The waste issue has thus been studied in several documents and the final conclusion of which it is stated that there is no permanent disposal waste needed if recycling is applied. But recycling of fusion reactor materials is far to be obvious regarding mostly the very high specific activity of the materials to be handled, the types of materials and the presence of tritium. Objectives Study the possible ways of recycling fusion materials and analyse the challenges of the materials management from fusion reactors, based on current practices used in fission reactors and the requirements for the manufacture of fusion equipments. Principal results Specific activity of fusion materials 6,50E+11 6,00E+11 1,E+12 3,31E+11 1,E+11 4,19E+11 Fusion materials 1,E+10 3,95E+10 decay (log scale) 1,E+09 1,E+08 6,55E+08 1,E+07 Current limits g / 1,E+06 Blanket module Bq Divertor 1,E+05 Fission current 1,E+04 practices 20000 1,E+03 1,E+02 200 100 75 1,E+01 1,E+00 Studsvik Siempelkamp Duratek Centraco Facility A comparison of fusion materials requirements and current fission practices concerning the recycling of metals. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Raw Material Value A comparison between fusion and fission reactor materials for recycling: the raw material value and the specific activity are rather different and require different approaches. All steps of the recycling process were discussed with experts of existing melting facilities for radioactive materials in Western Europe and the United States and some of the manufacturers of complex pieces for fusion reactors like blanket and divertor modules. These exchanges of information showed clearly the difficulties and challenges to be faced to allow future recycling of fusion materials. Starting from components composition, function and expected activation, the feasibility of every step of a recycling process has been analysed: dismantling, melting, re-fabrication, etc. The main challenges to be faced were listed as follows: the types of materials to be handled (W, Be, Cu,...) are not common for the current foundries and can request special procedures and processes; the high level of specific activity (see figure) can bring issues in the off-gas treatment, the material handling (to be remote) and the oven maintenance; the separation of the different materials, tightly joined together by various means, can also be difficult to perform; up to now, the recycling of tungsten for instance is never applied; the metallurgy of this metal requires specific and complex steps, not easy to carry out remotely; the manufacture of fusion reactor parts requires rather complex bonding and linking of different materials (e.g. W+Cu+stainless steel) coupled with tight mechanical tolerances; this process can be hard to carry out remotely. The challenges and issues being identified, the various ways of recycling fusion materials and the necessary nuclear data being available, it is now possible to evaluate the different potential options and the best ways to proceed with this problem. One of the main results is also the identification of the necessary R&D areas allowing to analyse the feasibility of the planned recycling of materials and reduction of radioactive waste generation. Future developments Evaluating the recycling options requires a detailed study of the overall material cycle occurring in a fusion plant during its exploitation: i.e. the different recycling paths, the timing aspects (recycling continuously during operation or at decommissioning time), using interim "decay" store or not and how long, etc. Alternative ways to close the material cycle loop will also have to be analyzed. Main contact person Luc Ooms [email protected] ; Vincent Massaut [email protected] . Main reference L.Ooms, V.Massaut,"Feasibility of Fusion Waste Recycling", January 2005, Report R-4056 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 EXTERNAL ADVISORY COMMITTEES External advisory committees continuously evaluate the scientific programmes of SCK•CEN. Their members are selected by the board of governors among the academic world and among senior actors of the nuclear community. SCIENTIFIC ADVISORY COMMITTEE (SAC) Yvan Bruynseraede - chairman Katholieke Universiteit Leuven em. Michel Giot – vice chairman Université Catholique de Louvain-la-Neuve Benoit De Boeck Association Vinçotte Nucléaire Fred Decamps Former ONDRAF/NIRAS (Belgian Agency for Radioactive Waste and Enriched Fissile Materials) Frank Deconinck SCK•CEN Paul Govaerts SCK•CEN Chris Huyskens Universiteit Eindhoven Frans Moons SCK•CEN Ernest Mund Université Libre de Bruxelles Jacques Sinnaeve Former European Commission Etienne Vansant Universiteit Antwerp DEPARTMENTAL ADVISORY COMMITTEES (DAC'S) DAC - Radiation Protection & Site Restoration DAC – Reactor Safety, Materials & Fuels Chris Huyskens - chairman Universiteit Eindhoven Benoit De Boeck – chairman Association Vinçotte Augustijn Janssens European Commission Nucléaire Mark Loos SCK•CEN William D’haeseleer Katholieke Universiteit Patrick Smeesters FANC/AFCN (Federal Leuven Agency for Nuclear Control) Pierre D’hondt SCK•CEN Hubert Thierens Universiteit Gent Didier Haas European Commission Hans Vanmarcke SCK•CEN Edgard Koonen SCK•CEN Micheline Kirch-Volders Vrije Universiteit Brussel Jacqueline Lecomte-Beckers Université de Liège André Wambersie Université Catholique de Tim van der Hagen Universiteit Delft Louvain-la-Neuve em. Georges Van Goethem European Commission Luc Vanhoenacker Suez Energy Internationall DAC – Radioactive Waste, Dismantling & Radiochemistry Etienne Vansant – chairman Universiteit Antwerpen Guy Collard SCK•CEN Peter De Preter ONDRAF/NIRAS (Belgian Agency for Radioactive Waste and Enriched Fissile Materials) Jean Fuger Université de Liège em. Véronique Halloin Université Libre de Bruxelles Alex Hermanne Vrij Universiteit Brussel Alain Sneyers SCK•CEN Harry Vereecken Forschungszentrum Jülich/Universität Bonn www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 MEMBERS OF THE BOARD OF SCK•CEN SCK•CEN is governed by a board of governors. The board has the widest ranging authority to perform all management and disposition actions related to SCK•CEN. Chairman Vice Chairmen Managing Director Michel Giot Frank Deconinck Claude Truffin Paul Dirven Members Léon Bindler – Henri Bonet – Yvan Bruynseraede - Kurt Debruyne – Bart De Moor – Georges Denef – Jan Huylenbroeck – Laurent Jacquet – Raf Suys Honorary member Government Commissioners Observers of the Trade Union Karel Dieltjens Renaat Hanssens Baron André Jaumotte Tom Vanden Borre Jacky Dekeyser Redy de Leege General Manager Secretary Paul Govaerts Joseline Leroy www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 DOCTORAL THESIS PREPARED AT SCK•CEN AND DEFENDED IN 2004 Name Steven Lierman Subject A legal analysis of the use of ionising radiation in medical hospital practice: an inquiry into the influence of prevention and precaution on health protection and liability. University University of Antwerp Faculty Law Date January 14, 2004 Promotor Thierry Vansweevelt SCK•CEN Mentor Ludo Veuchelen Abstract From a legal perspective there exists a clear need for a general framework describing conditions and consequences of risk management in the field of high technology. Despite the existence of many kinds of Safety Procedures and Soft Law, specific guidelines are lacking for regulators and courts, especially in case of scientific controversy and uncertainty about the health effects of an activity or a product such as low doses of ionising radiation, electro-magnetic fields, genetically modified organisms, PCB's in salmon etc. The research of the PISA Project on Legal Aspects and Liability has been focussed on the medical applications of ionising radiation. The safety approach depends on the risk characterisation and differs for stochastic and deterministic effects. The most important objective was to find liability or funding systems which can cope with these differences, in particular between dose limits (as for the nuclear industry), reference dose levels foreseen in the EC medical Directive (as for nuclear medicine), and Optimisation referring to the ALARA principle. Risk assessment and risk management that are based on traditional narrow risk-assessment models have to be revised in the light of the Precautionary Principle. This principle urges policy-makers to adopt a broader, more pluralistic approach, considering the societal equilibrium, i.e. the general interest of the activity at stake, the general impact of individual protective measures and the existence of “reasonable” alternatives from a sociological, economical, scientific and technological point of view. One of the characteristics of the Precautionary Principle relates to our opinion to the "collective" damage to human health, i.e. a detriment that relates to a group of people. Nevertheless, as a result of the application of the Precautionary Principle, we believe that in case of individual damage the standard of care shall be more and more defined, following the risk characterisation and assessment which has to be introduced once a scientific or societal problem occurs with regard to medical practices, already subject to the legal duty of Justification and of Informed Consent. For some specific cases, as paediatric CT doses, the 2003 report of the Belgian Health Council gives a clear warning and refers to collective doses that are significantly higher than in the neighbouring countries. It cannot be denied that such a repeated warning urges decision makers and hospitals to take corrective actions, in particular when poor optimisation is put in place. Causality in the nuclear field is another complex problem, where worldwide alternatives are under consideration, such as “probability of causation”. However, such a concept, based on statistical proof, can hardly be implemented in Belgian law since our tort- and insurance-system is based on the individual relationship between liable actor and victim. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 DOCTORAL THESIS PREPARED AT SCK•CEN AND DEFENDED IN 2004 Name Delécaut Grégory Subject The geochemical behaviour of uranium in the Boom clay University Université Catholique de Louvain Faculty Faculté des Sciences Date June 28, 2004 Promotor Prof. Ph. Sonnet SCK•CEN Mentor Pierre De Cannière Abstract In Belgium, the Boom Clay is currently studied as the reference host formation for the disposal of high-level and long-lived radioactive waste. In case of direct disposal of spent fuel, uranium isotopes are important contributors along with their daughters to the dose rate at very long term. Therefore, it is essential to study the migration of uranium in the host formation. The present work contributes to improve the knowledge of uranium speciation in the Boom Clay, U(IV) versus U(VI), and of the mechanisms controlling the uranium mobility such as solubility, sorption and complexation by organic matter. The information necessary to interpret the migration behaviour is derived from the study of naturally occurring uranium in the rock and from laboratory experiments conducted under conditions representative for the Boom Clay. Uranium naturally present in the Boom Clay is concentrated in detrital heavy minerals and in authigenic iron(II)-bearing minerals such as siderite and glauconite. Despite its reducing capacity, pyrite is surprisingly depleted in uranium relative to the mean content. Furthermore, uranium is also associated with the surfaces of clay minerals. The clayey fraction contains about 4 ppm uranium and is the main contributor to the total uranium content of the Boom Clay since it constitutes up to 60 wt. % of the rock. The correlation observed on the field between uranium and organic matter suggests that uranium is reduced, likely during the early diagenesis process of bacterially-mediated sulphate reduction. If hexavalent oxidation state of uranium predominates as predicted by geochemical calculations based on the most recent thermodynamic data of the Nuclear Energy Agency (NEA), less than 5% of uranium is complexed by humic acids in the Boom Clay pore water. The U(VI) speciation is dominated by the inorganic 4- carbonate complexes, merely UO2(CO3)3 . The conditional constant determined for the complexation of U(VI) by humic acids under in situ Boom Clay conditions is log? ?exp = 12.4 l·eq-1. However, experimental 4- studies show that UO2(CO3)3 is reduced by interaction with pyrite, the main reducing mineral present in the rock, and precipitates as a mixed oxide of U(IV)/U(VI), i.e. UO2+x. Moreover, electromigration experiments suggest that U(VI) is not stable in the Boom Clay: U(VI) is reduced and precipitates as U(IV) oxy-hydroxides. The experimentally measured solubility of U(IV) amorphous oxide, UO2(am), in Boom Clay pore water is about 10-8 mol·l-1. This solubility value is not increased by complexation of U(IV) with dissolved organic matter. The dominant effect of organic matter on the dissolution of UO2(am) is the stabilisation of U(IV) real colloids which increase the uranium concentration by three orders of magnitude. However, the mobility of these colloids is expected to be very limited because of the compaction level of the Boom Clay and its ultra- filtrating feature. The diffusive transport of dissolved uranium is furthermore retarded by significant sorption onto clay minerals. In conclusion, the presence of organic matter in the Boom Clay has no negative effect on the uranium retention which is dominated by the solubility and sorption of U(IV) species. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 DOCTORAL THESIS PREPARED AT SCK•CEN AND DEFENDED IN 2004 Name Isabelle Fucks Subject The safety culture according to a “comprehensive approach” A contribution to Risk Governance within complex systems University Université de Liège Faculty Faculté de Sciences Politiques Date October 1, 2004 Promoter Prof. Dr. Catherine Zwetkoff, ULg SCK•CEN Mentor Frank Hardeman Abstract This PhD is based on two evolutions within the society concerning the way to manage modern risks. It is more and more acknowledged that, firstly, rational scientific models are no longer capable to explain and manage the complexity and the diversity of risks. Secondly the supporters of a democratic conception of the risk governance claim that the risk management can benefit from the participation of the lay people to the debate. Within this framework, the study of « safety culture », according to a bottom-up and comprehensive approach, in the field of the social sciences, represents an opportunity to make concrete the risk governance principle within complex system (such as a nuclear power plant and a nuclear research centre). The objectives of this PhD are the following: to appreciate the participation of the workers to the debate of the risk management within organisations; to present the lessons which can be drawn from this exercise and finally to investigate the safety culture of different groups of workers adopting an alternative view as compared to the vision as formulated in the present texts of the IAEA. The methodology was based on two techniques: observation and Focus Group. The observations were planed to feed further the Focus Group discussions with concrete examples of situations at work. We organized different Focus Group discussions with different kinds of workers (workers, managers, safety officers) in order to collect the social representation relating to the safety, the organization, the technology, the socio-economical environment and the work of each of these groups, both in the Belgian Nuclear Research Centre and in the Nuclear Power Plant of Tricastin in France. The results confirm firstly the relevance of developing a multidisciplinary theoretical framework of safety culture drawing its inspiration from sociology, social psychology, anthropology, etc. This multidisciplinary approach allows conferring to the human factor concept the complexity to integrate its different dimensions, such as the real-life situations at work. The results relate also to the pertinence, for organizations but also for politics in charge of the elaboration of a risk management policy, to consider the points of view of workers. At the political level, a question emerges from the results: How can politics (re)intervene in the effective risk management? One of the propositions is to promote a reflexive approach among people in charge of the daily risk management upon their practices and methods of risks management. The main results illustrate what can be safety culture within organizations and propose the co-existence of three different kinds of safety culture: between workers, managers and safety officers. They present the safety culture as a product of social interactions between workers, organization, technology, work, safety and the socio-economical context. These different variables shape the safety culture but also they singularize it. The author would like to acknowledge all the persons who have participated to this study such as the participants to the study, who dedicated time for explaining their job and their organization. My acknowledgment goes particularly to Frank Hardeman, Catherine Zwetkoff and Michel Llory. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 DOCTORAL THESIS PREPARED AT SCK•CEN AND DEFENDED IN 2004 Name Gunter Bombaerts Subject A positionism epistemology applied to small group decision-making in radioactive waste management University Ghent University Faculty Arts and philosophy Date November 26, 2004 Promotor Johan Braeckman SCK•CEN Mentor Geert Volckaert, Bernard Neerdael Abstract Assuring the safety of technological developments is becoming one of the most important tasks in society. For nuclear waste repositories, it is important to know what will remain valuable of current performance and safety assessments within a few hundred years. The core of the PhD concerns the meaning that can be attributed to safety assessments. This study develops a new philosophical theory to explain how "small group decision-making" on technoscientific problems takes place. It is applied to the specific problem of decision-making on radioactive waste disposal and its related risk assessment. The new philosophical theory is based on Latour's interactionism theory, which in its essence states that facts are only facts if they are accepted by the network. The theory adds that fact-building or decision-making happens in a certain context by interaction of different context elements. The word context has a very specific meaning. It refers to a problem solving situations in which individuals work out a problem framing and use attitudes, personalities, group cultures, and objects. Decisions or fact-building within the group will happen by interaction between these context elements that will get different hierarchical positions and lead to contextual dissonance reduction. This is called positionism. An international questionnaire has been carried out asking for estimations by technologists and scientists of the risks and uncertainties of a high level waste repository on the one hand and their personality, group culture and background characteristics on the other hand. Two important indicators occur. High neuroticism - a personality measure indicating the general tendency to experience affects such as fear, sadness, or distrust- correlates with high assessments of the waste repository risks. Scientists with high confidence in science give significant lower estimations of the repository risks. These results illustrate in a qualitative way the contextual point of view of the philosophical theory. Observations of the Belgian low level waste decision-making process have been made over a period of four years. These observations do not give an historical construction of the process but are used as an illustration of positionism mechanisms. They show that certain argumentations on technology are positioned above others because of contextual aspects. These results illustrate in a qualitative way the positionism theory and its actual applications. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 AWARDS BEST UNIVERSITY AND COLLEGE FINAL-YEAR THESES Very keen to encourage high-quality research, the Belgian Nuclear Research Centre grants several awards. SCK•CEN attributes yearly prizes of respectively 1 500 and 1 000 € to the best university and the best college final-year theses carried out in its laboratories. In 2003 the award for the best university theses was granted to: Name Koen Windey Titel Thesis Emergency cooling system for MYRRHA Universiteit BNEN/KULeuven Mentor: Baudouin Arien Promotor: Michel Giot The award for the best final-year theses was granted to: Name Koen Stappers Titel Thesis Berekeningssoftware voor de radiale verdeling van temperaturen en spanningen in cilindersecties Hogeschool Katholieke Hogeschool Kempen Mentor: Philippe Gouat Promotor: Luk Schepers SCK•CEN'S SCIENTIFIC AWARD - PROFESSOR ROGER E. VAN GEEN SCK•CEN allocates every two years 12 500 € to the best original work in nuclear research. The selection is performed by the Belgian National Fund for Scientific Research (NFWO/FNRS). For details see http://www.sckcen.be. PHD CANDIDATES & POST-DOCTORAL RESEARCHERS - SELECTION 2004 PHD Name Research Topic Reactor materials Kevin Govers Atomic modelling of degradation effects in ceramic nuclear fuels. Anton Stuer Mechanismen voor spanningscorrosie, onder invloed van straling, voor roestvaste stalen in een PWR omgeving en hun gebruik in eindige elementen toepassingen. Joris Van den Bosch ADS-candidate materials compatibility with Liquid Metal in n- irradiation environment. Microbiology Felice Mastroleo Proteomic and genomic analysis on the effects of spaclight related environmental conditions on the photosynthetic bacterium Rhodospirillum rubrum ATCC25903 used in Life Support System. Fusion Inge Uytdenhouwen Degradation of plasma facing materials under ITER relevant loading conditions. Radiation protection Kristien Smans The development of dose optimisation strategies for X-ray examinations of newborns. Radio-ecology Caroline Vincke Contribution to long term biosphere impact modelling in a geological disposal scenario through measurements of soil- tree-atmosphere water transfer and related ecophysiological parameters. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 SCIENTIFIC OUTPUT AND VISITORS IN 2004 OUTPUT The SCK•CEN scientific output can be consulted on our website '95 '96 '97 '98 '99 '00 '01 '02 '03 '04* International journals 31 34 43 42 50 50 52 54 65 87 Publications National journals 4 5 6 9 2 7 11 3 6 12 Proceedings 33 56 46 55 60 49 37 73 98 67 International Presentations 101 153 104 82 119 95 121 173 199 186 Conferences National presentations 13 36 17 6 17 18 20 31 37 31 International posters 17 45 28 23 38 38 18 40 62 66 Contract reports 78 77 136 119 SCK•CEN reports (restricted) 118 82 61 62 98 62 9 17 19 15 Reports SCK•CEN reports (public) 31 10 14 11 5 5 27 24 23 22 External contract reports 19 19 38 16 24 36 16 25 39 24 Preprints 4 3 1 2 (Parts of) books 4 12 7 6 8 12 18 12 18 13 Patents 3 4 2 1 1 3 1 0 0 0 Doctorate theses 1 2 2 4 5 5 5 2 3 4 Theses Final-year theses (university) 15 19 5 2 3 4 8 11 8 15 Final-year projects (college) 17 18 10 17 13 11 18 14 9 15 Participation in expert groups 7 7 8 3 9 9 11 11 12 9 Training courses 6 3 13 12 10 8 11 19 25 22 Miscellaneous output 9 14 11 6 10 3 25 17 24 16 TOTAL 429 519 415 357 472 415 490 606 784 725 * partial results as of December 31, to be completed and confirmed later VISITORS Visits Type EIG EURIDICE BR1 BR2 BR3 LHMA SCH RP Total * 39 Industry: Nuclear 82 58 91 10 22 6 30 218 15 Industry Other 0 11 10 14 18 0 0 53 4 Political 35 17 0 0 2 0 0 37 3 Press 25 2 2 2 0 0 0 27 50 Scientists 167 12 30 40 31 35 22 273 18 Socio-economical 273 54 89 3 0 0 58 288 81 Students 382 267 210 104 134 47 39 914 6 Miscellaneous 18 0 3 0 1 0 28 50 216 982 421 435 173 208 88 177 1860 * several groups visited more than one building EIG EURIDICE Underground Research Facility and Demonstration hall EURIDICE BR1 Research reactor BR2 Materials testing reactor BR3 Dismantled PWR LHMA Laboratory for High and Medium Level Activity SCH Chemistry labs RP Radiation protection labs www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 EVENTS IN 2004 Conferences December 13, 2004 Link between past and present research conducted at SCK•CEN on ferritic alloys and steels and their application in nuclear systems. November 30, 2004 Seminar: High Temperature Electrochemistry in Light Water Reactors EFC event Nº 279 September 23-25, 2004 "Flow and Beyond" Cytometry: From Pathogenesis to Therapy - From Clinical Research to Environmental Biology Jun 23, 2004 First VISIPLAN Users day - VISIPLAN and ALARA principles: feedback of users and new trends May 3-4, 2004 International Workshop on Information Systems for Crisis Response and Management Topical days November 23, 2004 From MYRRHA towards XT-ADS Radiation sensitivity of mammalian germ cells and early embryos: recent May 18, 2004 results and new perspectives March 25, 2004 Knowledge Management in a Scientific environment Monthly Lunch talks December 17, 2004 Fusion … Any other R&D area with such a long term perspective? A funded playground for Nuclear Research Centres! Fusion energy. An "ethical" perspective. Fusion Programme at SCK•CEN. The fusion "roadmap" and the "Who is who?". November 26, 2004 From Base to Byte: Bioinformatics explained. Multi-scale building physics : from pore to micro climate. October 29, 2004 Evaluating the Effects of Ionizing Radiation on Gene Expression in the Developing Mouse Brain. Ethical approach to decommissioning: what is acceptable for next generations? September 17, 2004 Destructive Radiochemical and Chemical Analysis of Nuclear Research and Industrial Materials at NCS. Optically stimulated luminescence of α-Al2O3:C for dosimetric applications. May 28, 2004 International Inspections for the Verification of the Non Proliferation Treaty. Actual cases in (non) proliferation of nuclear weapons: North Korea, Iran, Iraq, Libya … March 26, 2004 The Tree Mile Island accident. Harrisburg, Pennsylvania, March 28, 1979. Already 25 years ago! Is dismantling an exciting job? February 20, 2004 Safety analyses of MYRRHA with the RELAP code. BEWISE : Belgian Woman in Science January 30, 2004 Master of Science in Nuclear Engineering www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 TRAINING ISRP (INTERNATIONAL SCHOOL FOR RADIOLOGICAL PROTECTION) January 27, ‘Basisbegrippen kernfysica’ and 'Interactie van straling met materie', September 28 Posthogeschoolvorming Stralingsprotectie, Katholieke Hogeschool Brugge-& December 21 Oostende (KHBO) March 17 Cursus Bescherming tegen radioactieve straling (Dutch); Association Nationale pour la Protection contre l’Incendie et l’Intrusion (ANPI) April 19-23 & May 3-6 Grondige cursus Stralingsbescherming (for Lemmens Services; later ISS Industrial Services) April 27 Cours Radioactivité (French); Association Nationale pour la Protection contre l’Incendie et l’Intrusion (ANPI) June 7-11 Training Course on Euratom Article 35 Verifications for the European Commission, DG-TREN, Luxembourg June 28 – July 9 Regional Training Course on the Safe Transport of Radioactive Material, at the request of the International Atomic Energy Agency (IAEA), with cooperation of the Federal Agency for Nuclear Control (FANC-AFCN) September 13-17 Training session 'Radiological Protection' - open registration (French) (Transnubel, Agence Fédérale de Contrôle Nucléaire (AFCN), Institut National des Radioéléments (IRE), SCK•CEN) September 17 ‘Algemene wetgeving inzake stralingsbescherming’, Opleiding Stralingsprotectie, Vormingscentrum HIVSET, Turnhout September 27 & ‘Wetgeving inzake stralingsbescherming’, Posthogeschoolvorming December 20 Stralingsprotectie, Katholieke Hogeschool Brugge-Oostende (KHBO) October 4-8 Training session ‘Radiological Protection’ - open registration (Dutch) (Belgonucléaire, NIRAS, Belgoprocess, Federaal Agentschap voor Nucleaire Controle (FANC), Electrabel, SCK•CEN) October 29 ‘Algemene principes stralingsprotectie en dosimetrie’, Permanente vorming Stralingsprotectie, Katholieke Hogeschool Kempen (KHK), Lier October 21, 22 & 25 Basic course on radiological protection for the European Commission (EuropeAid) December 10 'Ionizerende stralingen', opleiding 'technicus arbeidshygiëne', PREVENT, Antwerpen Throughout 2004 Organisation of and contribution to the second academic year of the ‘Radiological Protection Expert Training’ in co-operation with the XIOS Hogeschool Limburg OUTLOOK ON FUTURE COURSES ORGANISED BY THE ISRP IN 2005 February 21-24 Cursus stralingsbescherming (opfrissing) voor (ervaren/minder ervaren) agenten stralingscontrole (for Electrabel KC Doel) June 20-30 Grondige cursus stralingsbescherming (for Electrabel KC Doel) September 19-23 Cours de Radioprotection - open registration (French) October 10-14 Cursus Stralingsbescherming - open registration (Dutch) Throughout 2005 Organisation of and contribution to the third academic year of the ‘Radiological Protection Expert Training’ in co-operation with the XIOS Hogeschool Limburg www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 OUTLOOK ON FUTURE TOPICAL DAYS Academic year 2004 – 2005 May 3, 2005 Stochastic methods in Applied Science Outlook on Academic year 2005 – 2006 October 7, 2005 Life management for current research reactors November 8, 2005 Heavy liquid metal technology December 6, 2005 Clay formations and geological disposal of radioactive waste February 7, 2006 Trends and developments in irradiation technology February 21, 2006 Improvement of techniques for multiscale modelling Outlook on Academic year 2006-2007 November 7, 2006 Interaction: radiation – semiconductor materials November 21, 2006 Waste characterization needs and practices: for free release, reception, intermediate storage, long term management December 5, 2006 Emergency Planning (Benelux) February 6, 2007 Experience with full scale MCNP modeling of research reactors February 27, 2007 Minimising waste production in a complex nuclear center: from conception to the decommissioning; the SCK•CEN reference case. WORKSHOPS, CONFERENCES, COURSES... ORGANISED BY SCK·CEN April 18-20, 2005 International Workshop on Information Systems for Crisis Response and Management May 22-25, 2005 3rd International Workshop on SPACE MICROBIOLOGY June 27-29, 2005 6th MEGAPIE - Technical Review Meeting August 21-26, 2005 12th International Conference on Emerging Nuclear Energy Systems September 12-15, 2005 MRS 2005: 29th Symposium on the Scientific Basis for Nuclear Waste Management November 23 - 25, 2005 3th International Conference on Education and Training in Radiological Protection INTERUNIVERSITY PROGRAMME IN NUCLEAR ENGINEERING ORGANISED WITHIN THE FRAMEWORK OF THE BELGIAN NUCLEAR HIGHER EDUCATION NETWORK (BNEN). BNEN is an interuniversity programme in a collaboration between SCK•CEN and the Vrije Universiteit Brussel, VUB, Universiteit Gent, UGent, Katholieke Universiteit Leuven, KULeuven, Université de Liège, ULg, Université Catholique de Louvain, UCL. After successful completion of the programme the academic degree "Masters of Science in Nuclear Engineering" is awarded. Courses Nuclear energy: introduction Nuclear fuel cycle and applied radiochemistry Introduction to nuclear physics Nuclear materials I Nuclear reactor theory and experiments Nuclear materials II Nuclear thermal-hydraulics Radiation protection and nuclear measurements Operation and control Advances courses (on the above topics) Reliability and safety Project and internship ENEN (EUROPEAN NUCLEAR ENGINEERING NETWORK) The partners in the FP5 European Nuclear Engineering Network organised themselves in a sustainable non- profit-making organisation to deliver the European master of Nuclear Engineering, to promote PhD studies in nuclear engineering, to encourage exchange of students and professors, to establish a framework for mutual recognition, to foster and strenghten the relationship with research laboratories, industry and regulatory bodies. The courses on Nuclear Thermal Hydraulics, Nuclear Reactor Theory and Radiation Protection of the Belgian academic postgraduate programme on nuclear engineering are organised in a modular way and taught in English to facilitate and enhance participation of European students. The courses make full use of the laboratories and infrastructure of SCK•CEN. In total some 25 students, of which 30% from abroad, participated in the courses. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Radiation Protection Division Scientific Output 2004 Contents Decision Strategy Research - Emergency Management and Policy Support ...... 1 Safeguards and Physics Measurements...... 3 Low radioactivity Measurements...... 4 Radiation protection research ...... 4 Radiobiology and microbiology ...... 4 Epidemiology...... 11 Radiological assessments...... 11 Radon and enhanced natural radioactivity...... 11 Radioecology...... 12 Decision Strategy Research - Emergency Management and Policy Support Publications H. Aage, P. Astrup, K. Bargholz, M. Drews, H. Joergensen, U. Korsbech, B. Lauritzen, T. Mikkelsen, S- T. Nielsen, C. Rojas Palma, R. Van Ammel "Experimental evaluations of gamma fluence-rate predictions from Argon-41 releases to the atmosphere over a nuclear research reactor site" Rad. Prot. Dosim. (2004) Vol. 108 N°2, pp 161-168 C. Rojas-Palma, F. Hardeman, H. Miska, T. Duranova, H. Cabanekova "Better use of european (regional) resources" Radiation Protection Dosimetry (2004), Vol. 109, Nos 1-2, pp. 115-117 C.M. Vandecasteele "Environmental monitoring and radioecology: a necessary synergy" Journal of Environmental Radioactivity N°72 (2004) pp 17-23 F. Hardeman, "Environmental monitoring in the vicinity of the mol-dessel site (belgium): a historic overview" Proceedings of the INSINUME 2004 conference (In-situ Nuclear Metrology), 27-30 September 2004, Albena, Bulgaria F. Hardeman, D.C.W. Sanderson, A.J. Cresswell, A. Debauche, "An airborne gamma-ray spectrometry survey of nuclear sites in Belgium" Journal of Environmental Radioactivity 72 (2004) pp 213-224 C.M Vandecasteele, "Radioactive contamination of aquatic ecosytem: source, transfer ans countermeasures" in: "Risk Assessment as a Tool for Water Resources Decision Making in Central Asia, C.M. Teaf et al. (eds.), Kluwer Academic Publishers, 2004, pp. 133 - 154 A. Sohier, K. van der Meer, F. Hardeman, "Radiological Dispersion Devices: Prevention, Preparedness and Response - an Overview" Proceedings of the IRPA 11 conference, Madrid 23-28 May 2004 Presentations B. Carlé, "The use of the HINES communication tool in an on-site emergency response room" ISCRAM 2004, Brussels, 3-4 May 2004 C. Turcanu "Structuring stakeholders' involvement in radiological crisis management" , ISCRAM2004 Proceedings, Brussels, 3-4 May 2004 F. Hardeman, "Medische interventies binnen het noodplan - deel 1", Conferentie: Ongewenste verspreiding van radioactieve bronnen, Brussel, 23 oktober 2004 Organisatie: Koninklijke Academie voor Geneeskunde van België; Koninklijke Vlaamse Academie voor Wetenschappen en Kunsten; Belgische Vereniging voor Stralingsbescherming F. Hardeman, "Problématique de la contamination de l'eau en cas d 'accident nucléaire ou radiologique" Conference: Intérêt d'une surveillance radiologique en temps réel des eaux de surface et souterraines, IRE Fleurus, 22 juin 2004, Belgique F. Hardeman, "Radiological Surveillance in the vicinity of the Mol-Dessel site" IAEA Technical Meeting 26420 on Monitoring of Radioactive Discharges to the Environment, IAEA Vienna, March 15-19, 2004, Austria A. Sohier, "TC-OSEM: An integrated set of training courses for off-site emergency management in Europe" Internatioal symposium on off-site nuclear emergency management, Rhodes, Greece, 21 – 24 September 2004 C. Rojas-Palma, Finn Ugletbeit and Vince McClelland, "Building Regional Capabilities to Assist and Improve Response to Nuclear and Radiological Emergencies", International symposium on off-site nuclear emergency management, Rhodes, Greece, 21 – 24 September 2004 C. Rojas-Palma et al., "Data information exchange prototype for nuclear emergency response: status and future perspectives", International symposium on off-site nuclear emergency management, Rhodes, Greece, 21 – 24 September 2004 Reports C. Turcanu, P. Astrup, R. O. Puchrto, C. Rojas-Palma "Data assimilation in the early phase: Kalman filtering RIMPUFF" EC contract FIKR-CT-2000-00025 RODOS(RA5)-TN(04)-01 B. Carlé, F. Hardeman "Een multi-criteria analyse als ondersteuning van MONA vzw bij de keuze tussen een oppervlakteberging of een diepe berging voor laag radioactief afval in de gemeente Mol" BLG 994 contract nr CO 90 04 1776.00 MONA F. Hardeman, J. Ruts, A. Sohier, C. Rojas-Palma,,F. Joppen, P. Antoine, F. Vermeersch, "Noodplanscenario's voor de installaties van het SCK•CEN - Expertiseopdracht ten behoeve van de Provincie Antwerpen" Contract-report R3863 A. Sohier, T. Zeevaert, "Berekening van de dosisbelasting in de omgeving ten gevolge van hypothetische ongevallen met inwendige oorzaak in de MOX fabriek van Belgonucléaire te Dessel" Contract-report R-3953 Conference organisation B. Carlé, B. Van de Walle "ISCRAM2004 International Workshop on Information Systems for crisis Response and Management." SCK•CEN Brussels, Proceedings 3 – 4 May 2004 Training course A. Sohier, "Training Course on Preparedness and Response for Nuclear or Radiological Emergencies" SCK•CEN - Mol, 21-25 June 2004, Nuclear emergency management Thesis H. Neele "How to use a knowledge portal as an enabler for knowledge dissemination in a community of emergency managers" Thesis Tilburg University, the Netherlands, SCK•CEN mentor: B. Carlé S. Thorel "Réalisation d'un portal de gestion de données pour "l'Environmental Monitoring" Thesis Université du Littoral, SCK•CEN mentor: B. Carlé Safeguards and Physics Measurements Publications F. Vanhavere, A.L. Lebacq, P. Kockerols,J. Gasparra, M. Hult; H. Janssens; G. Lövestam, "Neutron field measurements for ALARA purposes around a van de graaff accelerator building" Proceedings, Radiation Protection Dosimetry Vol. 11; issue 1-4, pp. 711-715 M. Coeck, T. Bolognese-Milsztajn, D. Bartlett, M. Boschung, G. Curzio, d'Errico, A. Fiechtner, V. Giusti, V. Gressier, J. Kyllönen, V. Lacoste, L. Lindborg, M. Luszik-Bhadra, C. Molinos, G. Pelcot, M. Reginatto, H. Schuhmacker, R. Tanner, F. Vanhavere, D. Derdau, "Individual neutron monitoring in workplaces with mixed neutron/photon radiation" Proceedings, Radiation Protection Dosimetry Vol. 11; issue 1-4 F. Vanhavere, "The tissue equivalent proportional counter as a tool for characterising mixed neutron- gamma fields" Annalen van de Belgische vereniging voor Stralingsbescherming, Vol. 29, N° 2, 2004, pp. 187-198, ISSN-0250-5010 P. Vermaercke, P. Robouch, N. Younes, "The "Naji Plot", a simple graphical tool for the evaluation of inter-laboratory comparisons" Proceeding of PTB-IT-10 (April 2003) F. Vanhavere, D. Huyskens, L. Struelens, "Peripheral neutron and gamma doses in radiotherapy with an 18 mv linear accelerator" Radiation Protection Dosimetry (2004), Vol.110, Nos1-4, pp. 607-612 L. Struelens, F. Vanhavere, H. Bosmans, R. Van Loon, "Effective doses in angiography and interventional radiology: calculation of conversion factors for angiography of the lower limbs" The British Journal of radiology, 78 (2005) 1-8 Presentations F. Vanhavere, T. Bolognese; Milsztajn; M. Ginjaune, "Active Methods Instruments for personal dosimetry of external radiation present situation in Europe and future needs" IRPA11 conference Madrid 24-28/05/2004 K. van der Meer, "The threat of a dirty bomb and possible verification measures" 25th annual symposium on safeguards and nuclear material management, 13-15 May 2003, Stockholm P. Vermaercke, "The QA/QC concept introduced at SCK.CEN in R&D-projects on the characterisation of Nuclear Waste Packages" Koninklijke Vlaamse Chemische Vereniging Food Division, In co-operation with Centrum voor Landbouwkundig Onderzoek CLO, Symposium-Workshop, Accreditation in research and development, Melle, 20/10 and 27/10/2004 L. Struelens, F. Vanhavere, H. Bosmans, R. Van Loon, "Analysis of patient doses in interventional radiology Primary author Keywords patient dose and interventional radiology" Dimond III Image Quality and Dose Management for Digital Radiography - Leuven, België, 25-27 maart 2004 L. Struelens, F. Vanhavere, H. Bosmans, R. Van Loon, "Skin dose measurements on patients for diagnostic and interventional neuroradiology: multicentre study" Optimaisation Strategies in Medical X- Ray Imaging Second Malmö Conference on Medical X-Ray Imaging - Malmö Sweden 23-25 April 2004 L. Struelens, F. Vanhavere, H. Bosmans, R. Van Loon, "Skin dose measurements on patients for diagnostic and interventional procedures of the head: multicentre study" 11th International Congress of the international radiation protecion association (IRPA) - Widening the Radiation Protection World. Madrid, 23-28 mei 2004 F. Vanhavere, D. Berus, P. Covens, N. Buls, M. Van den Broeck, G. Van Holsbeeck, "Extremity Doses during Manipulation of Radiopharmaceuticals" International Congress of the international radiation protecion association (IRPA) - Widening the Radiation Protection World. Madrid, 23-28 mei 2004 Reports J. Verstricht, "IAEA Expert Group on Safeguards for Final Disposal of Spent Fuel in Geological Repositories - Belgian Contribution" Belgian Support Programme to the IAEA, task JNT C 01273 BEL, Contract report R-3838, february 2004 P. Vermaercke, L. Sneyers, "Certification of As and Se in Oyster Tissue by ko-NAA Primary author Keywords Certification of As and Se in Oyster Tissue by ko-NAA" Contract-report R-3993 september 2004 P. Vermaercke, L. Sneyers, "Homogeneity of a dry-mixed GM maize powder samples" Contract-report R-3990, august 2004 P. Vermaercke, L. Sneyers, "CCQM-K44, CCQM-P70, EUROMET 784, IMEP-21 and IRMM CRM, Cr, Cu and Zn in Sewage Sludge by k0-NAA" Contract-report R-4042 october 2004 P. Vermaercke, "Certification of As and Mn in Rice by ko-NAA" Contract-report R-3907 august 2004 P. Vermaercke, "Homogeneity and certification of As and Se in Salmon by ko-NAA" Contract-report R-3975 august 2004 P. Vermaercke, H. Aigner, P. Bode, J.P. Doherty, A. Fajgelj, M. Rossbach, B. Smit, "Quality System Implementation for Nuclear Analytical Techniques" Contract Report IAEA-TCS-24, ISSN 1018-5518, july 2004 Low radioactivity Measurements Report C. Hurtgen, G. Etherington, C. Cossonnet, D. Franck, J.L. Genicot, J-R. Jourdain, B. Le Guen, T. Rahola, J. Sovijärvi, G.N. Stradling, E. Ansoborlo, P. Bérard, "Optimisation of Monitoring for Internal Exposure (OMINEX)" EC contract report N° NRPB-W60, ISBN 0 85951 541 9 August 2004 Radiation protection research Radiobiology and microbiology P.S. All the references annotated with an (*) are parts of C007 project. Books L. Hendrickx, S. Wuertz "Investigating in situ natural genetic transformation of Acinetobacter sp. BD413 in biofilms with confocal laser scanning microscopy" in Genetic Eng., Kluwer Acad./Plenum Publ., Ed. J.K. Setlow, Vol. 26, 159-173, 2004. (*) Publications I. Adriaens, R. Cortvrindt, J. Smitz "Differential FSH exposure in preantral follicle culture has marked effects on folliculogenesis and oocyte developmental competence", Hum. Reprod., 19(2):398-408, 2004. S. Baatout, H. Derradji "Cytometric methods to analyze radiation effects", J. Biol. Regul. Homeost. Agents, 18(2):101-5, 2004. S. Baatout, H. Derradji, P. Jacquet, D. Ooms, A. Michaux, M. Mergeay "Effect of curcuma on radiation- induced apoptosis in human cancer cells", Int. J. Oncol., 24(2):321-9, 2004. S. Baatout, P. Jacquet, H. Derradji, D. Ooms, A. Michaux, M. Mergeay "Study of the combined effect of X-irradiation and epigallocatechin-gallate (a tea component) on the growth inhibition and induction of apoptosis in human cancer cell lines", Oncol. Reports, 12(1):159-67, 2004. S. Baatout, H. Derradji, P. Jacquet, D. Ooms, A. Michaux, M. Mergeay "Enhanced radiation-induced apoptosis of cancer cell lines after treatment with resveratrol", Int. J. Molec. Med., 13(6):895-902, 2004. S. Bekaert, H. Derradji, S. Baatout "Telomere biology in mammalian germ cells and during development", Dev. Biol., 274:15-30, 2004. M.A. Benotmane "Molecular aspects of individual radiosensitivity", J. Biol. Regul. Homeost. Agents, 18(3), 2004. L. de Saint-Georges "Biological Effects of Low Dose Ionizing Radiation- the Never-ending Story" Strahlenschutz Praxis 3, 47-50, 2004. L. de Saint-Georges "Low dose ionizing radiation exposure: Understanding the risk for cellular transformation", J. Biol. Regul. Homeost. Agents, 18(2): 96-100, 2004. V. Huguet, M. Mergeay, E. Cervantes, M.P. Fernandez "Diversity of Frankia strains associated to Myrica gale in Western Europe: impact of host plant (Myrica vs. Alnus) and of edaphic factors", Environ. Microbiol., 6(10):1032-41, 2004. (*) P. Jacquet “Sensitivity of germ cells and embryos to ionizing radiation”, J. Biol. Regul. Homeost. Agents, 18(2):106-114, 2004. N. Leys, L. Hendrickx, P. De Boever, S. Baatout, M. Mergeay "Space flight effects on bacterial physiology", J. Biol. Regul. Homeost. Agents, 18(2):193-9, 2004. (*) M. Mori, C. Desaintes "Gene expression in response to ionizing radiation: an overview of molecular features in hematopoietic cells", J. Biol. Regul. Homeost. Agents, 18(3), 2004. M. Mori, M.A. Benotmane, D. Vanhove, P. Van Hummelen, E.L. Hooghe-Peters, C. Desaintes "Effect of ionizing radiation on gene expression in CD4+ T lymphocytes and in Jurkat cells: unraveling novel pathways in radiation response", Cell Mol. Life Sci., 61, 1955-1964, 2004. I. Noel-Georis, T. Vallaeys, R. Chauvaux, S. Monchy, P. Falmagne, M. Mergeay, R. Wattiez "Global analysis of the Ralstonia metallidurans proteome: prelude for the large-scale study of heavy metal response", Proteomics, 4(1):151-79, 2004. (*) F. Thierry, M.A. Benotmane, C. Demeret, M. Mori, S. Teissier, C. Desaintes "A genomic approach reveals a novel mitotic pathway in papillomavirus carcinogenesis", Cancer Res. 64, 895-903, 2004. Presentations I. Adriaens, P. Jacquet "The guinea pig: an interesting model to study radiation effects in female germ cells", Radiation Sensitivity of Mammalian germ cells and early embryos, Topical day, Mol, 18/5/2004. V. Auquier, S. Monchy, R. Wattiez, M. Mergeay, J. Ruysschaert, G. Vandenbussche "Identification of new membrane proteins involved in the resistance mechanisms to copper and silver in Ralstonia metallidurans CH34", Int. Meet., Copper homeostasis and its disorders: molecular and cellular aspects, Ischia, Italy, 23-28/10/2004. (*) S. Baatout, R. Wattiez, L. Hendrickx, N. Leys, A. Dams, M. Mergeay "Bacterial physiology changes after pH stress", Belg. Soc. for Microbiology, Brussels, 3/12/2004. S. Baatout "La cytométrie en flux et la microbiologie: généralités, applications, avantages et limitations", Belg. Soc. for Analytical Cytology, 28/10/2004. S. Baatout, "Flow cytometric analysis of radiation effects", 4th Euroconf. ‘Flow & Beyond’, Mol, 23- 25/9/2004. S. Baatout, J. Buset, M. Neefs, A. Michaux, H. Derradji, M. Mergeay, P. Jacquet "Comparison of the gastrula stage in two mouse strains with different radiation sensitivities", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. S. Baatout, S. Micuda, H. Derradji, R. Benotmane, J. Martinkova, M. Mergeay "Epigallocatechin gallate, the main component of tea polyphenol, affects the X-ray induced apoptosis in human IM-9 cells", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. S. Baatout, H. Derradji, P. Van Oostveldt, M. Mergeay, S. Bekaert "Apoptosis induced by X-irradiation or hydrogen peroxide is associated with an up-regulation of Bcl-2 and an activation of caspase-3 in two leukemic cell lines", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. S. Baatout, R. Wattiez, L. Hendrickx, N. Leys, A. Dams, M. Mergeay "pH induced changes on bacterial physiology", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. S. Baatout, J. Buset, M. Neefs, A. Michaux, H. Derradji, M. Mergeay, P. Jacquet "Cell cycle and caspase-3 activity after X-irradiation at the mouse gastrula stage", Belg. Soc. of Biochemistry and Molecular Biology, Brussels, 12/11/2004. S. Baatout, J. Buset, M. Neefs, A. Michaux, M. Mergeay, P. Jacquet, "Short term genetic and cellular effects of X-irradiation in gastrulas from normal and p53-deficient mice", Gemrate Meet., Roma, Italy, 13-14/12/2004. S. Baatout, J. Buset, M. Neefs, A. Michaux, H. Derradji, M. Mergeay, P. Jacquet "A comparison of the radiation sensitivities of embryos at the gastrula stage in two mouse strains", Eur. Soc. for Radiation Biology, Budapest, Hungary, 25-28/8/2004. S. Baatout, S. Micuda, H. Derradji, R. Benotmane, J. Martinkova, M. Mergeay "Epigallocatechin gallate affects the X-ray induced apoptosis in human IM-9 cells", Eur. Soc. for Radiation Biology, Budapest, Hungary, 25-28/8/2004. S. Bekaert, T. De Meyer, E. Rietzschel, M. De Buyzere, S. Baatout, T. Gillebert, P. Van Oostveldt "Seizing human biological age", EMBO Workshop, 58th Harden Conf., Telomeres and Genome Stability, Cambridge, UK, 3-7/4/2004. S. Bekaert, H. Derradji, P. Van Oostveldt, M. Mergeay, P. Jacquet, S. Baatout "Telomere shortening in malformed p53-mutant mouse fetuses after irradiation", 4th Euroconf. ‘Flow & Beyond’, Mol, 23- 25/9/2004. S. Bekaert, M. Deruelle, S. De Smet, H. Derradji, P. Van Oostveldt, M. Mergeay, S. Baatout "Accelerated telomere attrition after oxidative stress in human cancer cell lines in the presence of spirulina", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. M. A. Benotmane, M. Mori, J. Verheyde, W. Schoonjans, M. Mergeay "SCK•CEN human and mouse high density chips and radiobiology", ULB seminars, Campus Erasme, Brussels, 27/5/2004. M. A. Benotmane, M. Mori, J. Verheyde, W. Schoonjans, A. Michaux, M. Mergeay "Microarrays to analyse radiation effects", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. M. A. Benotmane, A. Michaux, W. Schoonjans and M. Mergeay "Microarray set up and study of radiosensitivity in the human population", VWR Int. Customer event, Leuven, 26-28/10/2004. L. de Saint-Georges "Radiobiology, basic concepts", Radiation Sensitivity of Mammalian germ cells and early embryos, Topical day, Mol, 18/5/2004. L. de Saint-Georges, J. Verheyde, M.A. Benotmane, M. Mergeay "Radiation induced apoptosis in the E15 embryonic mouse brain", Eur. Soc. for Radiation Biology, Budapest, Hungary, 25-28/8/2004. L. de Saint-Georges "Low dose ionizing radiation exposure: Understanding the risk for cellular transformation", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. L. de Saint-Georges, J. Verheyde, M.A. Benotmane, M. Mergeay "Radiation induced apoptosis in the Embryonic mouse brain", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. R. GrayMerod, L. Hendrickx, M. Hausner, S. Wuertz "Quantitative and Spatial Assessment of Natural Transformation in Acinetobacter sp. BD413 Biofilms Using In Situ Confocal Microscopy and Image Analysis", Horizontal Gene Flow in Microbial Communities, Workshop, Warrenton VA, 14- 16/06/2004.(*) R. GrayMerod, L. Hendrickx, L.N. Mueller, J.B. Xavier, S. Wuertz "Effect of nucleic acid stain Syto 9 on nascent biofilm architecture of Acinetobacter sp. BD413", Int. Conf. on BIOFILMS 2004, Las Vegas, NV, USA 24-26/10/2004. (*) L. Hendrickx, N. Leys "Bacterial Physiology during Space Flight", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. L. Hendrickx, P. De Boever, M. Mergeay "Toegepast microbiologisch ruimtevaartonderzoek in SCK•CEN in Mol", Flemish Space Days, Ostend, 20-22/02/2004. L. Hendrickx, S. Baatout, R. Wattiez, A. Wilmotte, P. Janssen, J. Pérez, A. Montràs, N. Leys, F. Marty, C. Paillé, M. Mergeay "Monitoring microbiology in the micro-ecological life support system alternative (MELiSSA)", Int. Symp. on Microbial Ecology, Cancun, Mexico, 22-27/08/2004. L. Hendrickx, S. Baatout, R. Wattiez, A. Wilmotte, P. Janssen, J. Pérez, A. Montràs, N. Leys, F. Marty, C. Paillé, M. Mergeay "Monitoring microbiology in the micro-ecological life support system alternative (MELiSSA)", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. L. Hendrickx, A. Van Havermaat, M. Mergeay "PNA blocked PCR analysis to detect contaminants in a R. rubrum ATCC25903 culture", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. L. Hendrickx, F. Mastroleo, S. Baatout, R. Wattiez, A. Wilmotte, P. Janssen, N. Leys, C. Paille, M. Mergeay "Monitoring microbiology in the biological life support system MELISSA (Micro-Ecological Life Support System Alternative)", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. (*) P. Jacquet, S. Baatout, J. Buset, M. Neefs, A. Michaux, M. Mergeay "Short term genetic and cellular effects of x-irradiation in gastrulas from normal and p53-deficient mice", EULEP Meet., Cambridge, UK, 20/09/2004. P. Jacquet “Genetic susceptibility to radiation-induced effects in embryos”, Topical Day on “Radiation sensitivity of mammalian germ cells and early embryos: recent results and new perspectives”, Mol, 18/05/2004. P. Jacquet “Sensitivity of germ cells and embryos to ionizing radiation”, 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. P. Jacquet, I. Adriaens, J. Buset, M. Neefs, M. Mergeay “Studies on the radiosensitivity of the mouse oocyte using an early preantral follicle culture system”, Eur. Soc. for Radiation Biology, Budapest, p.127, 25-28/8/2004. P. Jacquet, I. Adriaens, J. Buset, M. Neefs, M. Mergeay “Radioadaptive response in mouse female germ cells”, 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. P. Jacquet, S. Baatout, J. Buset, M. Neefs, A. Michaux, M. Mergeay, "Cytogenetic and cellular effects of X-irradiation in early embryos", Gemrate Meet., Roma, Italy, 13-14/12/2004. P. Janssen, A. Enright, B. Audit, I. Cases, L. Goldovsky, N. Harte, V. Kunin, C. Ouzounis "The COmplete GEnome Tracking database: an update", Genomes 2004, Hinxton, Cambridge, United Kingdom, 14-17/4/2004. (*) P. Janssen, A. Enright, B. Audit, I. Cases, L. Goldovsky, N. Harte, V. Kunin, C. Ouzounis "The COmplete GEnome Tracking database: an update", Belg. Bioinformatics Conf., Brussels, 23/4/2004. (*) P. Janssen, A. J. Enright, B. Audit, I. Cases, L. Goldovsky, N. Harte, D. Ahren, V. Kunin, C. A. Ouzounis "“CC”-COGENT: Two hundred completely sequenced and published genomes unified in one mySQL database", Symp. Belg. Soc. for Microbiology, Brussels, 3/12/2004. (*) N. Leys, R. Wattiez, S. Baatout, P. De Boever, P. Cornelis, S. Aendekerk, M. Mergeay "Over- expression of the DpsA protein as a response of Ralstonia metallidurans CH34 to space flights and its role in bacterial physiology", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. (*) N. Leys S. Monchy, R. Wattiez, P. Janssen, R. Benotmane, S. Baatout, P. De Boever, P. Cornelis, A. Dams, W. Schoonjans, M. Mergeay "Functional genomics of Ralstonia metallidurans CH34", Genomes 2004, The Wellcome Trust Conf. Centre, Hinxton, Cambridge, UK, 14-17/4/2004. (*) N. Leys, R. Wattiez, S. Baatout, P. De Boever, M. Mergeay "Gene expression in Ralstonia metallidurans CH34 in space", Habitation 2004 Conf., Orlando, Florida, USA, 4-7/1/2004. (*) N. Leys, R. Wattiez, S. Baatout, P. Janssen, P. De Boever, A. Dams, S. Aandekerk, P. Cornelis, M. Mergeay "MESSAGE: Microbial Experiments in a Space Station for the Analysis of Gene Expression", 3rd Astrobiology Science Conf., NASA, CA 94035-1000, USA, 28/3-1/1/2004. (*) N. Leys, L. Hendrickx, R. Wattiez, S. Baatout, P. De Boever, P. Cornelis, S. Aendekerk, M. Mergeay "Bacterial physiology in space", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. (*) N. Leys, R. Wattiez, S. Baatout, P. Janssen, P. De Boever, A. Dams, M. Mergeay "MESSAGE: Microbial experiments in the space station about gene expression", 10th Int. Symp. on Microbial Ecology, Cancun, Mexico, 25-27/2004. (*) N. Leys, R. Wattiez, S. Baatout, P. De Boever, A. Dams, M. Mergeay "Gene expression in Ralstonia metallidurans CH34 in space flight", Eur. Symp. on Environmental Biotechnology, 26-28/04/2004, Ostend, 2004. (*) F. Mastroleo, L. Hendrickx, S. Baatout, N. Leys, L. de Saint-Georges, R. Wattiez, M. Mergeay "Analysis of the effects of space flight related environmental conditions on the photosynthetic bacterium Rhodospirillum rubrum ATCC25903 used in live support systems", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. F. Mastroleo, L. Hendrickx, S. Baatout, N. Leys, L. de Saint Georges, R. Wattiez, M. Mergeay "Analysis on the effects of spaceflight on the photosynthetic bacterium Rhodospirillum rubrum ATCC25903 used in Life Support Systems", Belg. Soc. for Microbiology, Brussels, 03/12/2004. M. Mergeay " Response of Ralstonia metallidurans CH34 to space flights", MELISSA Yearly Meet. ESTEC Noordwijk, The Netherlands, 13-14/5/2004. (*) M. Mergeay "Ralstonia metallidurans: a bacterium adapted to anthropogenic environments", Seminar ,Laboratoire d'Ecologie Microbienne Université Claude Bernard LYON1, France, 13/9/2004. (*) M. Mergeay "Microbiologie spatiale: enjeux et perspectives", Seminar at the Université de Liège (Centre d'Ingénierie des Protéines: CIP), 5/11/2004. (*) M. Mergeay, N. Leys, P. De Boever, C. Lasseur "Microbial presence and activity during long haul space flights", NASA Microbial Workshop, Kennedy Space Center (Florida, USA), delegate of the ESA party, 17-19/2/2004. (*) S. Monchy, R. Benotmane, T. Vallaeys, D. van der Lelie, J. Gouzy, M. Mergeay "Sequence analysis of the two plasmids pMOL28 and pMOL30 harbouring R. metallidurans CH34 heavy metal resistance specificities", Molecular Microbiology Conf., Exploring prokaryotic diversity, Heidelberg, Germany, 22- 26/04/2004. (*) S. Monchy, N. Leys, R. Wattiez, P. Janssen,R. Benotmane, S. Baatout, P. De Boever, P. Cornelis, A. Dams, W. Schoonjans, M. Mergeay "Functional genomics of Ralstonia metallidurans CH34: genetic flexibility and adaptation to its environment", Conf. on Integrating Metabolism and Genomics, Montréal, Canada, 30/04/2004-03/05/2004. (*) S. Monchy, S. van Aelst, A. Benotmane, R. Wattiez, T. Vallaeys, M. Mergeay "Towards a functional analysis of the copper resistance cluster in Ralstonia metallidurans pMOL30 plasmid", Belg. Soc. for Microbiology, Brussels, 3/12/2004. (*) S. Monchy, D. van der Lelie, S. McCorkle, S. Taghavi, J. Dunn, M. Mergeay "The four replicons of Ralstonia metallidurans CH34 revealed by IS reassembly", Belg. Soc. for Microbiology, Brussels, 3/12/2004. (*) M. Mori "Gene expression in response to ionizing radiation: an overview of molecular features in hematopoietic cells", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. M. Mori, I. Tirone, D. Vanhove, M.A. Benotmane, E.L. Hooghe-Peters, C. Desaintes "Differential gene modulation induced by ionising radiation in human lymphocyte subsets", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. M. Mori, M. A. Benotmane, E. L. Hooghe-Peters, F. Thierry, C. Desaintes "Combined effects of irradiation and papillomavirus E2 proteins on the cell cycle of HeLa cells", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. M. Mori "Changes in gene expression in different human cell types after irradiation", Microarray Technology: Genome - Proteome Function course, EMBL, Heidelberg, Germany, 29/5-5/6/2004. J. Verheyde, M.A. Benotmane, L. de Saint-Georges, P. Van Hummelen, M. Mergeay, L. Leyns "Global Gene-Expression in Mouse Brain Embryo as result of ionizing radiation exposure", 7th Int. Meet. of the Microarray Gene Expression Data Soc., Toronto, Canada, 8-10/9/2004. J. Verheyde "Evaluating the Effects of Ionizing Radiation on Gene Expression in the Developing Mouse Brain", Inter Univ. Attraction Pole Meet., ULB, Gosselies, 19/11/2004. J. Verheyde "Evaluating the Effects of Ionizing Radiation on Gene Expression in the Developing Mouse Brain", Lunch-talk, SCK-CEN, Mol, 15/10/2004. J. Verheyde "Evaluating the Effects of Ionizing Radiation on Gene Expression in the Developing Mouse Brain", BEMS Meet., Brussels, 10/12/2004. R. Wattiez, N. Leys, P. Falmagne, P. Janssen, M. Mergeay "Ralstonia metallidurans: a new aceton tolerant bacterium", ASM Conf. on Integrating Metabolism and Genomics, Montreal, Canada, 30/4- 3/5/2004. (*) Reports M. A. Benotmane "Human individual radiosensitivity; Heritability and Genetics “RaHGe”", EC contract FIGH-CT-2002-00216, 2004 report. M. A. Benotmane "Human individual radiosensitivity; Heritability and Genetics “RaHGe”", EC contract FIGH-CT-2002-00216, mid-term report, October 2004. P. De Boever, D. Hanus, J. Mahillon, M. Mergeay "Complementary Scientific Investigations in the frame of the project Microbial Detection in Air System for Space Applications-prephase 1", ESTEC contract 16370/02/NL/CK, Techn. note, 47 p, September 2004. P. De Boever, M. Mergeay "Microbial ecology in Space Stations. Review in the frame of the project Microbial Detection in Air System for Space Applications-prephase 1", ESTEC contract 16370/02/NL/CK, Techn. note, 67 p, September 2004. P. Jacquet, S. Baatout “Genetic factors predisposing to radiation-induction of mutation and malformations during early gestation: the role of DNA repair and cell cycle control”, EC contract FIGH- CT-2002-00210, mid-term report, June 2004. P. Jacquet, S. Baatout “Genetic factors predisposing to radiation-induction of mutation and malformations during early gestation: the role of DNA repair and cell cycle control”, EC contract FIGH- CT-2002-00210, 2004 report. Conference organization I. Adriaens, P. Jacquet "Topical Day on Radiation sensitivity of mammalian germ cells and early embryos: recent results and new perspectives", Mol, 18/05/2004. J.W. Gratama, S. Baatout, N. Schaaf-Lafontaine, "Flow and Beyond; Cytometry from pathogenesis to therapy, from clinical research to environmental biology", joint Euroconf. of the Eur. Working Group on Clinical Cell Analysis and the Belg. Soc. of Cytometry, Mol, 23-25/9/2004. Training course S. Baatout, L. Holmstock "Effets biologiques des rayonnements ionisants", training course isRP, SCK•CEN, Mol, 15-16/9/2004. M. Mergeay "Ecology of plasmids", VUB Campus Plein VUB Graduate School for Molecular Biology and Biotechnology, 20/11/2004. (*) M. Mergeay "Microbiologie des environnements influencés par l'homme: des sites industriels à la Station Spatiale Internationale (ISS) (et au-delà)", Fac. Univ. d'Agronomie de Gembloux, Doctoral School Biotechnology, 26/5/2004.(*) Thesis S. Andries "Studie van de functie en expressie van acx genen coderend voor aceton carboxylase in Ralstonia metallidurans CH34", Thesis Hogeschool Limburg, Diepenbeek (SCK•CEN mentor: N. Leys), June 2004. (*) V. Bossi "Etude de l'axenicité de Rhodospirillum rubrum dans le cadre du projet MELiSSA: Mise en evidence et caracterisation de contaminants", Thesis Univ. Blaise Pascal, Clermont-Ferrand, France (SCK•CEN mentor: L. Hendrickx) Sept. 2004. M. Deruelle "Celleefbaarheid en replicatieve veroudering in humane kankercellijnen onder oxidatieve stress en stralingsstress in aan- en afwezigheid van Spirulina", Thesis Fac. Landbouw, Univ. Gent (SCK•CEN mentor: S. Baatout), June 2004. S. Holthof "Opsporen van microorganismen en microbiële activiteit in luchtmonsters", Thesis Hogeschool Kempen, Geel (SCK•CEN mentor: P. De Boever), June 2004. K. Janssen "Statistical Analysis of Microarray Data", Thesis, Centre for Statistics, Univ. Limburg, Belgium (SCK•CEN Mentor: P. Janssen), June 2004. V. Kerstens "Kennismaking met de strategie om microbiële populaties in lucht te bepalen" Thesis industrial engineer, Hogeschool Kempen, Geel (SCK•CEN mentor: P. De Boever), June 2004. J. Luts "Setup of a Customized Microarray Analysis Flow using BioConductor", Thesis, Faculty of Agricultural and Applied Sciences, Univ. of Louvain (SCK•CEN Mentor: P. Janssen), June 2004 A. Van Havermaet "Evaluatie van PNA (peptide nucleic acid) geblokkeerde PCR analyse voor de detectie van contaminanten in een Rhodospirillum rubrum cultuur", Thesis Hogeschool Limburg, Diepenbeek (SCK•CEN mentor: L. Hendrickx), June 2004. Others S. Baatout, guest-editor of the issues 2 and 3 of the Journal of Biological Regulators and Homeostatic Agents, 2004. P. Jacquet, Eur. INSERM expert, in charge of the evaluation of ongoing and new research projects to be funded by the French National Institute of Health, 2004. Award F. Mastroleo, poster award "Analysis on the effects of spaceflight related environmental conditions on the photosynthetic bacterium Rhodospirillum rubrum ATCC25903 used in Life Support Systems", 4th Euroconf. ‘Flow & Beyond’, Mol, 23-25/9/2004. Epidemiology Radiological assessments Publications B. Kanyár, G. Pröhl, U. Bergström, B. Hallberg, S. Mobbs, G. Olyslaegers, P. Pinedo, I. Simon, T. Zeevaert, K. Eged, T. Katona "Modelling of the radioactive daughter elements in soil to assess radiation impact due to contaminated irrigation water by parents of 231Pa, 226Ra, 238U, 237Np and 239Pu", AARMS Radiation Technology 3 (5): 647-652, 2004. Reports L. Sweeck, Th. Zeevaert, H. Vanmarcke, M. Loos, A. Sohier, F. Vermeersch "Impactstudie van de radioactieve effluenten van Belgoprocess: huidige situatie en alternatieven", SCK•CEN Contract Report on behalf of NIRAS, R-3921, June 2004. International Atomic Energy Agency "Testing of environmental transfer models using data from the remediation of a radium extraction site", IAEA-BIOMASS-7, March 2004 (eds. L. Sweeck, Th. Zeevaert). G. Pröhl, G. Olyslaegers, T. Zeevaert, B. Kanyar, P. Pinedo, I. Simón, U. Bergström, B. Hallberg, S. Mobbs, Q. Chen, R. Kowe "Biosphere Models for Safety Assessment of Radioactive Waste Disposal", GSF-Bericht 06/04, Institut für Strahlenschutz, 2004. Th. Zeevaert, D. Mallants, F. Vermeersch, G. Volckaert "Impact verwijdering bronnen uit opslagplaats voor radiumhoudende afvalstoffen", SCK•CEN Contract Report on behalf of Umicore, R-3895, July 2004. Radon and enhanced natural radioactivity Books H. Vanmarcke, G. Eggermont, H. Mol, J. Brouwers “Hoofdstuk 2.6 Ioniserende straling”, Milieu- en natuurrapport Vlaanderen 2004, VMM, LannooCampus, Leuven, 2004, ISBN 90 209 5918 2, p 209- 218. Publications J. Paridaens, L. de Saint-Georges, H. Vanmarcke “Mitigation of a radon-rich Belgian dwelling using active subslab depressurization”, Environmental Radioactivity 79: 25-37, 2004. Presentations and conferences J. Paridaens “GPS-based handheld device for measuring environmental gamma radiation and mapping contaminated areas”, Int. Congress Series, ICS 1276, Invited papers of the 6th Int. Conf. on High Levels of Natural Radiation and Radon Areas, Osaka, Japan, September 6-10, 2004. J. Paridaens, H. Vanmarcke “Radiological impact of flue gas purification in a coal fired power plant in Belgium”, Radioactivity in the Environment series, Vol. 7, Elsevier, Proceedings NRE VII, ISBN 0 08 044137 8, 2004. I.V. Yarmoshenko, Z.S. Zunic, J.P. Mc Laughlin, J. Paridaens, I.A. Kirdin “Indoor radon long-term variation assessment”, Radioactivity in the Environment series, Vol. 7, Elsevier, Proceedings NRE VII, ISBN 0 08 044137 8, 2004. H. Vanmarcke, H. Mol, J. Paridaens, G. Eggermont “Exposure of the Belgian population to ionizing radiation”, Proceedings IRPA 11, http://www.irpa11.com/, Session 6d, contribution 20, Madrid, Spain, May 23-28, 2004. H. Vanmarcke “ICRP approach to the protection of plants and animals from the effects of ionizing radiation”, Ethique et radioprotection: SCK•CEN-UCL, Louvain-la-Neuve, September 28, 2004. Reports H. Vanmarcke, G. Eggermont, H. Mol, J. Brouwers “Achtergronddocument MIRA-T 2004: 2.6 Ioniserende straling”, Milieu- en natuurrapport Vlaanderen, VMM, http://www.milieurapport.be, p 79. P. Kockerols, H.Vanmarcke, M. Bovy, H. Drymael, G. Eggermont, H. Janssens, M. Sonck, M. Van Eijkeren “Comments BVS•ABR on the draft 2005 recommendations ICRP”, Comments submitted to ICRP, p 12, December 2004. Radioecology Publications F. Goor, Y. Thiry “Processes, dynamics and modelling of radiocaesium cycling in a chronosequence of Chernobyl-contaminated Scots pine (Pinus sylvestris L.) plantations”, The Science of the Total Environment 325: 163-180, 2004. G. Rufyikiri, S. Declerck, Y. Thiry “Comparison of 233U and 33P uptake and translocation by the arbuscular mycorrhizal fungus Glomus intraradices in root-organ culture conditions”, Mycorrhiza 14: 203-207, 2004. H. Vandenhove, F. Goor, S. Timofeyev, A. Grebenkov, Y. Thiry “Short rotation coppice as alternative land use for Chernobyl contaminated areas of Belarus”, Int. Journal for Phytoremediation 6(2): 139-156, 2004. H. Vandenhove, M. Van Hees “Phytoextraction for clean-up of low-level uranium contaminated soil evaluated”, Journal of Environmental Radioactivity 72: 41-45, 2004. M. Van der Perk, J. Burema, H. Vandenhove, F. Goor, S. Timofeyev “Spatial Assessment of the Economic Feasibility of Short Rotation Coppice on Radioactively Contaminated Land: Part: I. Model Description and Scenario Analysis”, Journal of Environmental Management 72: 217-232, 2004. M. Van der Perk, M., J. Burema, H. Vandenhove, F. Goor, S. Timofeyev “Spatial Assessment of the Economic Feasibility of Short Rotation Coppice on Radioactively Contaminated Land: Part II. Monte Carlo Analysis”, Journal of Environmental Management 72: 233-240, 2004. Presentations and conferences D. Jacques, D. Mallants, P. Seuntjes, M.Th. van Genuchten “Geochemical coupled transport code for variably staurated flow conditions: Metal leaching in podzol”, Int. Goldschmidt Conf., June 5-11, Copenhagen, Denmark, 2004. D. Mallants, H. Vandenhove “Modelling radionuclide and heavy metal mobility in uranium mill tailings in Kyrgyzstan”, Subsurface radionuclide migration-Case studies, organized by ITC and EAWAG, May, Zurich, Switserland, 2004. A. Straczek, N. Loosemore, J.F. Briat, P. Hinsinger, V. Sappin Didier, G. Vansuyt, G. Sarret, A. Manceau, B. Jaillard “Mobilization of zinc by Tobacco as a function of rhizosphere pH”, Int. Congress Rhizosphere 2004, September 12-17, Munich, Germany, LS 13/9, p. 54, 2004. I. Thijs, L. Diels, N. Maes, H. Vandenhove, D. Jacques, E. Smolders, D. Mallants “Laboratory testing of uranium removal efficiency of reactive media for use in groundwater remediation”, Eur. Geophysical Union, April 25-30, Nice, France, Geophysical Research Abstracts, Vol. 6, 07381, 2004. Y. Thiry, A. Gommers, B. Delvaux “Influence of K depletion and mineral alterability on root uptake of radiocaesium from mica”, Int. Congress Rhizosphere 2004, September 12-17, Munich, Germany, LS 13/3, p. 52, 2004. Y. Thiry, P. Schmidt, M. Van Hees, J. Wannijn, G. Rufyikiri, H. Vandenhove “Forest (re)vegetation impact on uranium cycling in mining area”, ECORAD 2004, September 6-10, Aix-en-Provence, France, 2004. Y. Thiry, M. Van Hees, P. Schmidt “Vegetation effect on pollutant recycling in uranium-mining area”, COST 859 workshop: Phytotechnologies to promote sustainable land use management and improve food safety, October 18-19, Warsaw, Poland, 2004. H. Vandenhove “Effect of soil physicochemistry on uranium speciation and availability to plants”, ECORAD 2004, September 6-10, Aix-en-Provence, France, 2004. H. Vandenhove “Feasibility of phytoremediation of NOR-contaminated sites”, Geomicrobiology in uranium waste remediation, October 3-6, Jena, Germany, 2004. Reports MYRRH “Use of mycorrhizal fungi for the phytostabilisation of radio-contaminated environments (FIGE- CT-2000-00014)”, Final Report, Co-ordinator: S. Declerck (UCL/MBLA/SOLS), Partners: C. Leyval (CNRS/LIMOS), I. Jakobsen (RISO/DPBB), Y. Thiry (SCK•CEN), 2004. H. Vandenhove “Eight Progress Report”, EC-TACIS Project N° SCRE1/N°38 Remediation of Uranium Mining and Milling Tailing in Mailuu Suu District Kyrgyzstan, Contract Report, SCK•CEN, Mol, R-3864, 36 p, 2004. H. Vandenhove “Nineth Progress Report”, EC-TACIS Project N° SCRE1/N°38 Remediation of Uranium Mining and Milling Tailing in Mailuu Suu District Kyrgyzstan, Contract Report, SCK•CEN, Mol, R-4054, 20 p, 2004. Thesis G. Somarikis “Accumulation of Radionuclides and Heavy Metals in Trees Growing on Afforested Uranium-Mining Deposits”, Ghent University, Interuniversity Programme in Physical Land Resources, 60 p, 2004. E. Van der Avoort “Effect van plantsoorten en bodemeigenschappen op de opname van uranium”, KHK, 62 p, 2004. Reactor Safety Division Scientific Output 2004 Contents Reactor Safety...... 1 Instrumentation Department...... 2 Reactor Physics & MYRRHA...... 5 Reactor Material Research...... 11 Reactor Safety Publications P. D'hondt, A. Aït Abderrahim, P. Kupschus, P. Benoit, E. Malambu, V. Sobolev, T. Aoust, K. Van Tichelen, B. Arien, F. Vermeersch, D. De Bruyn, D. Maes, W. Haeck, Y. Jongen, D. Vandeplassche, "MYRRHA, A Multipurpose Accelerator Driven System For R&D – Present Status", Seminar on Fission – Pont d'Oye V, Castle of Pont d'Oye, Habay-la-Neuve, Belgium, 16-19 September 2003, World Scientific, Proceedings 2004, ISBN 981-238-792-7 P. Baeten, H. Aït Abderrahim, P. D'hondt, B. Lance, P. Van Den Hende, D. Marloye, J. Basselier, "Critical Experiment with low-moderated MOX rods in VENUS", Publication in proceedings, The need for Integral Critical Experiments with Low-moderated MOX Fuels, Workshop proceedings, Paris, France, 14-15 April 2004, ISBN 92-64-02078-0 P. D'hondt, P. Baeten, L. Sannen, D. Marloye, B. Lance, A. Renard, J. Basselier, "The REBUS Experimental Programme For Burn-Up Credit", Proceedings of ICONE12, 12th International Conference on Nuclear Engineering, Arlington, Virginia, USA, April 25-29, 2004, ISBN 0-7918-3734-3 P. D'hondt, E. Sartori, J.B. Briggs, J. Gado, A. Hasegawa, I. Kodeli, F.J. Mompean, W. Wiesenack, A. Zaetta, "OECD/NEA Data Bank scientific and integral experiments databases in support of knowledge preservation and transfer", Publication in proceedings, International Conference on Nulcear Knowledge Management: Strategies, Information Management and Human Resource Development INSTN, CEA- Saclay, France, 7-10 September, 2004 Books Cyriel Wagemans, Jan Wagemans, P. D'hondt, Editors, "Seminar on Fission – Pont d'Oye V", Castle of Pont d'Oye, Habay-la-Neuve, Belgium, 16-19 September 2003, World Scientific, Proceedings 2004, ISBN 981-238-792-7 Da Ruan, Pierre D'hondt, Martine De Cock, Mike Nachtegael, Etienne E. Kerre, Editors, "Applied Computational Intelligence", World Scientific, Proceedings of the 6th International FLINS Conference, Blankenberge, Belgium, September 1-3, 2004, ISBN 981-238-873-7 Presentations P. Baeten, H. Aït Abderrahim, P. D'hondt, B. Lance, P. Van Den Hende, D. Marloye, J. Basselier, "Critical Experiment with low-moderated MOX rods in VENUS", The need for Integral Critical Experiments with Low- moderated MOX Fuels, Paris, France, 14-15 April 2004 P. D'hondt, P. Baeten, L. Sannen, D. Marloye, B. Lance, A. Renard, J. Basselier, "The REBUS Experimental Programme For Burn-Up Credit", 12th International Conference on Nuclear Engineering, Arlington, Virginia, USA, April 25-29, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 P. D'hondt, B. Carluec, "The European Project PDS-XADS 'Preliminary Design Studies of an Experimental Acccelerator-Driven System'", HPPA-4, 4th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, Daejeon, Korea, 15-20 May, 2004 P. D'hondt, P. Baeten, B. Lance, D. Marloye, J. Basselier, "Advances in code validation for mixed-oxide fuel use in light-water reactors through benchmark experiments in the VENUS critical facility", ICAPP'04, Pittsburgh, Pennsylvania, USA, June 13-17 2004 Instrumentation Department Publications A. Gusarov, F. Liegeois, "Experimental study of a tunable fiber ring laser stability", Optics Communications 234, 2004, pp. 391-397 A. Fernandez Fernandez, A. Gusarov, B; Brichard, M. Decréton, F. Berghmans, P. Mégret, A. Delchambre, "Long-term radiation effects on fibre Bragg grating temperature sensors in a low flux nuclear reactor", Measurement Science and Technology 15, 2004, pp. 1506-1511 W. N. MacPherson, R. R. J. Maier, J. S. Barton, J.D.C. Jones, A. Fernandez Fernandez, B. Brichard, F. Berghmans, J.C. Knight, P. StJ. Russell, L. Farr, "Dispersion and refractive index measurement for Ge, B- Ge doped and photonic crystal fibre following irradiation at MGy levels", Measurement Science and Technology 15, 2004, pp. 1659-1664 B. Brichard, A. F. Fernandez, H. Ooms, F. Berghmans, M. Decréton, A. Tomashuk, S. Klyamkin, M. Zabezhailov, I. Nikolin, V. Bogatyrjov, E. Hodgson, T. Kakuta, T. Shikama, T. Nishitani, A. Costley, G. Vayakis, " Radiation-hardening techniques of dedicated optical fibres used in plasma diagnostic systems in ITER", Journal of Nuclear Materials 329-333, 2004, pp. 1456-1460 A. F. Fernandez, A. Gusarov, F. Berghmans, K. Kallli, V. Polo, H. Limberger, M. Beukema, P. Nellen, "Round-robin for fibre Bragg grating metrology during COST270 action", Proceedings of SPIE, Vol. 5465, 2004, pp. 210-216 A. Gusarov, A. Volchek, A. Dotsenko, "Anisotropic Structure Formation during Phase Separation of Heterogeneous Glass under Electric Field", Proceedings of XX International Congress on Glass, ISBN 4- 931298-43-5, 2004, ref. paper P-08-007 A. Gusarov, V. Arbuzov, A. Volchek, V. Lisitsyn, V. Yakovlev, "Optical Absorption induced by Pulsed Electron Radiation in Commercial Silicate Glasses", Proceedings of XX International Congress on Glass, ISBN 4-931298-43-5, 2004, ref. paper O-14-050 M. Van Uffelen, I. Genchev, F. Berghmans, "Wavelength dependence of the response of Si and InGaAs pin photodiodes under gamma radiation", Proceedings of SPIE, Vol. 5554, 2004, pp. 132-143 O. Volchek, A. I. Gusarov, A. V. Dotsenko, V. A. Tsekhomsky, "Concentration dependence of droplet deformation in a phase separation process under an electric field", Physical Review E, Third Series, Vol. 69, N°. 1, January 2004 R. Kotynski, M. Antkowiak, F. Berghmans, H. Thienpont, "Photonic Crystal Fibers with Anisotropic Refractive Index", Proceedings of the Optical Waveguide Theory and Numerical Modelling, ISBN 90-76- 54603, March 2004, pp. 69 M. Antkowiak, R. Kotynski, T. Nasilowski, F. Berghmans, H. Thienpont, "Numerical analysis of Bragg gratings in Photonic Crystal Fibers", Proceedings of the Optical Waveguide Theory and Numerical Modelling, ISBN 90-76-54603, March 2004, pp. 68 A. Goussarov, D. Doyle, M. Fruit, A. Volchek, "Methodology for Prediction of Near-Earth Space Radiation Effects on Optical Glasses", Journal of Spacecraft and Rockets, Vol. 41, No. 3, May-June 2004, pp. 377-380 B. Brichard, A. F. Fernandez, H. Ooms, P. Borgermans, F. Berghmans, "True dose rate enhancement effect in phosphorous doped fibre optic radiation sensors", 2nd European Workshop on Optical Fibre Sensors, Proceedings of SPIE, Vol. 5502, 2004, June 2004, pp. 184-187 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 F. Fernandez, G. Rego, A. Gusarov, B. Brichard, J.L. Santos, H. M. Salgado, F. Berghmans, "Evaluation of long-period fiber grating temperature sensors in nuclear environments", 2nd European Workshop on Fibre Sensors, Proceedings of SPIE, Vol. 5502, June 2004, pp. 88-91 M. Van Uffelen, A. Giraud, F. Berghmans, "High gamma dose assessment of a multimode analogue fiber optic transmitter", Proceedings of RADECS 2004, September 2004, pp. 143-146 B. Brichard, A. Gusarov, A. Fernandez Fernandez, H. Ooms, F. Berghmans, M. Van Uffelen, "Optical characteristics of erbium-doped fibres operating in a gamma radiation field", Proceedings of RADECS 2004, September 2004, pp. 139-141 A. Fernandez Fernandez, B. Brichard, A. Gusarov, H. Ooms, C. Van Ierschot, F. Berghmans, M. Fokine, M. Popov, "Behaviour of chemical composition gratings in a very harsh mixed gamma neutron irradiation field", Proceedings of RADECS 2004, September 2004, pp. 97-100 M. Van Uffelen, S. Girard, F. Goutaland, A. Gusarov, B. Brichard, F. Berghmans, "Gamma Radiation Effects in Er-Doped Silica Fibers", IEEE Transactions on Nuclear Science, Vol. 51, No. 5, October 2004, pp. 2763-2769 B. Brichard, H. Ooms, J. Starckx, A. Fernandez Fernandez, M. Van Uffelen, F. Berghmans, "SCK•CEN gamma irradiation facilities for radiation testing in high-vacuum conditions", Proceedings of RADECS 2003, ESA SP-536, IEEE 03TH8776, October 2004, pp. 513-515 M. Van Uffelen, S. Girard, F. Goutaland, A. Gusarov, B. Brichard, F. Berghmans, "Gamma radiation effects in Er-doped silica fibers", Proceedings of RADECS 2003, SP-536, IEEE 03TH8776, October 2004, pp. 83-88 B. Brichard, A. Fernandez Fernandez, H. Ooms, F. Berghmans, "Study of the radiation-induced optical sensitivity in erbium and aluminium doped fibres", Proceedings of RADECS 2003, ESA SP-536, IEEE 03TH8776, October 2004, pp. 35-38 A. Fernandez Fernandez, B. Brichard, H. Ooms, F. Berghmans, "Gamma dosimetry using Red 4034 Harwell dosimeters in mixed gamma-neutron environments", Proceedings of RADECS 2003, ESA SP-536, IEEE 03TH8776, October 2004, pp.517-521 Books M. Van Uffelen, "IEEE Transactions on Nuclear Science, Vol. 51, No. 5, October 2004 Presentations J. Palmer, P. Agostini, M. Irving, E. Martin, M. Siuko, A. Tesini, M. Van Uffelen, " Remote Maintenance of the ITER Divertor", American Nuclear Society 10th International Conference on Robotics ans Remote Systems for Hazardous Environments, March 28-31, 2004, University of Florida, Gainesville, Florida M. Van Uffelen, I. Genchev, F. Berghmans, "Reliability study of photodiodes for their potential use in future fusion reactor environments", Photonics Europe, 26-29 April, 2004, Strasbourg, France B. Brichard, A. F. Fernandez, H. Ooms, P. Borgermans, F. Berghmans, "True dose rate enhancement effect in phosphorous doped fibre optic radiation sensors", Poster presentation EWOFS'04, June 9-11, 2004, Santander, Spain A. F. Fernandez, G. Rego, A. Gusarov, B. Brichard, J.L. Santos, H.M. Salgado, F. Berghmans, "Evaluation of long-period fiber grating temperature sensors in nuclear environments", Poster Presentation EWOFS'04, June 9-11, 2004, Santander, Spain M. Van Uffelen, I. Genchev, F. Berghmans, "Wavelength dependence of the response of Si and InGaAs pin photodiodes under gamma radiation", Photonics for Space Environments IX, August 2-3, 2004, Denver, Colorado, USA I. Genchev, M. Van Uffelen, F. Berghmans, K. Panajotov, H. Thienpont, "Gamma-radiation Induced Effects in Optoelectronic Materials and Structures – Modeling approaches", EDS 2004, September 10-18, 2004; Chernogolovka, Russia www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 A. F. Fernandez, A. Goussarov, B. Brichard, F. Berghmans, M. Decréton, "Fiber optic sensors networks for environmental and safety monitoring of fusion reactors", Poster Presentation 23rd Symposium on Fusion Technology (SOFT), September 20-24, 2004, Venice, Italy A. Gusarov, L. Vermeeren, B. Brichard, R. Van Nieuwenhove, A. Fernandez Fernandez, H. Ooms, M. Decréton, F. Berghmans, "In-situ in-reactor testing of fusion materials and components", 23rd Symposium on Fusion Technology, September 20-24, 2004, Venice, Italy A. Gusarov, H. Ooms, "SCK•CEN in-situ radiation tests: prototype bolometers with Pt meander on alternative substrates and Radiation-Induced Electric Degradation (RIED)", IEA Satellite Meeting on Radiation Effects in Insulators, 23rd Symposium on Fusion Technology, September 20-24, 2004, Venice, Italy A. Gusarov, A. Volchek, A. Dotsenko, "Anisotropic structure formation during phase separation of heterogeneous glass under electric field", 20th International Congress on Glass, September 26-October 01, 2004, Kyoto, Japan A. Gusarov, A. Arbuzov, A. Volchek, V. Lisitsyn, V. Yakovlev, "Optical absorption induced by pulsed electron radiation in commercial silicate glasses", 20th International Congress on Glass, September 26- October 01, 2004, Kyoto, Japan M. Van Uffelen, I. Genchev, F. Berghmans, "Radiation Effets on Si and InGaAs p-i-n- photodiodes", ESA Workshop on Optical Wireless On-board Communications, September 29-30, 2004, Noordwijk, The Netherlands I. Genchev, M. Van Uffelen, F. Berghmans, K. Panajotov, K. Gill, H. Thienpont, "Gamma Radiation Induced Effects in Si p-i-n Photo Diodes", 5-th RD-50 meeting, October 13-18, 2004, Florence, Italy M. Van Uffelen, "R&D Efforts at SCK•CEN for Condition Monitoring with Optical Cables in Nuclear Environments", Workshop Wire Systems Aging Assessment and condition Monitoring, October 28, 2004, Zurzach, Switzerland Reports I. Genchev, "Review of radiation effects in optoelectronic semiconductor materials and devices", BLG-984, May 2004 A. Fernandez Fernandez, "Final Report of the 2003 Underlying Technology Activities – Assessment of Fibres for Fusion Applications – Vessel/In Vessel-Remote Maintenance – Physics Integration-Diagnostics", R-3932, June 2004 Thesis P. Rodeghiero, "Feasability study of an optical Raman Distributed Temperature Sensor (RDTS) in a nuclear environment", Master of Science in Nuclear Engineering, University of Liège, BNEN, year 2003-2004 K. Bemelmans, "Ontwikkeling van een meetopstelling voor de karakterisering van golflengteregelbare laserdiodes", KHK, Campus HIK Geel, Academiejaar 2003-2004 B. Melis, "Karakterisering van RADFET dosimeters bij hoge gammastralingsdosissen", KHK, Campus HIK Geel, Departement Industrieel Ingenieur en Biotechniek, Academiejaar 2003-2004 S. Harnist, "Développement et caractérisations de Détecteurs OSL (Optically Stimulated Luminescence", Université Montpellier II, Science et Techniques du Languedoc, année 2003-2004 Y. Descas, "Photobleaching of Irradiated Optical Fiber", Université Monpellier II, Maîtrise Electronique Electrotechnique et Automatique, Mention Electronique Promotion 2003 – 2004, année 2003-2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Reactor Physics & MYRRHA Publications Th. Aoust, J. Cugnon, "Effects of isospin and energy dependences of the nuclear mean field in spallation reactions", The European Physical Journal A, Vol. 21, pp. 79-85, 2004 D. Ruan, M. Gülbay, C. Kahraman, "A-cut fuzzy control charts for linguistic data", International Journal of Intelligent Systems, Vol. 19, N. 12, pp. 1173-1195, 2004 D. Ruan, Y. Xu, X. Zeng, "On normalization of comprehensive evaluation system with complex uncertain information", Journal of Donghua University, Vol. 21, N. 3, pp. 30-35, ISSN 1672-5220, 2004 D. Ruan, "The role of computational intelligence in sensory evaluation", Journal of Doghua University, Vol. 21, N. 3, pp. 21-25, ISSN 1672-5220, 2004 D. Ruan, C. Kahraman, C.E. Bozdao, A.F. Ozok, "Fuzzy sets approaches to statistical parametric and nonparametric tests", International Journal of Intelligent Systems, Vol. 19, pp. 1069-1087, 2004 D. Ruan, C. Kahraman, A. Beskese, "Measuring flexibility of computer integrated manufacturing systems using fuzzy cash flow analysis", Information Sciences, Vol. 168, pp. 77-94, 2004 D. Ruan, D. Roverso, "Enhancing cross-correlation analysis with artificial neural networks for nuclear power plant feedwater flow measurement", Real-Time Systems, Vol. 27, N. 1, pp. 85-96, 2004 D. Ruan, G. Büyüközkan, T. Ertay, C. Kahraman, " Determining the improtance weights for the design requirements in the house of quality using the fuzzy anaytic network approach", International Journal of Intelligent Systems, Vol. 19, N. 5, pp. 443-461, 2004 D. Ruan, G. Büyüközkan, C. Kahraman, "A fuzzy multi-criteria decision approach for software development strategy selection", International Journal of General Systems, Vol. 33, N. 2/3, pp. 259-280, 2004 D. Ruan, C. Kahraman, U. Cebeci, " Multi-attribute comparison of catering service companies using fuzzy AHP: the case of Turkey", International Journal of Production Economics, Vol. 87, pp. 171-184, 2004 D. De Bruyn, H. Aït Abderrahim, A. Van Cotthem, C. Ramaeckers, "Techiniques de construction d'une grande structure enterrée dans des sables aquifères - Cas du projet MYRRHA à Mol, Belgique Construction techniques for a large underground structure in aquifer sands – The MYRRHA project case, Mol, Belgium", Tunnels et Ouvrages en Souterrain, N. 182, pp. 77-83, March-April 2004 L. Cinotti (ANSALDO Nucleare), B. Giraud (FRAMATOME ANP), H. Aït Abderrahim, "The eXperimental accelerator driven system (XADS) designs in the EURATOM 5th FP", in proceedings of EURADWASTE'04, Luxembourg, 29 March-1 April, 2004. P. Baeten, H. Aït Abderrahim, P. D'hondt, B. Lance, P. Van Den Hende, D. Marloye, J. Basselier, "Critical Experiment with low-moderated mox rods in VENUS", The Need for Integral Critical Experiments with Low- moderated MOX Fuels, Workshop proceedings, Paris, France, 14-15 April, 2004, ISBN 92-64-02078-0) P. Baeten, H. Aït Abderrahim, "Measurement of kinetic parameters in the fast subcritical core MASURCA", Nuclear Engineering and Design, Vol. 230, Issues 1-3, pp. 223-232, May 2004 D. De Bruyn, "Ongoing activities in Belgium in the field of ads", Working material limited distribution of IAEA Technical Meeting to "Review of National Programmes on Fast Reactors & Accelerator Driven Systems (ADS)"; Technical Working Group on Fast Reactors, IAEA-TM-26677, TWG-FR/118, Vienna, Austria, 10- 14 May 2004 W. Voorbraak, T. Kekki, J. Wagemans, T. Seren, M. van Bocxstaele, J. Woittiez, "Retrospective dosimetry of fast neutrons focussed on the reaction 93Nb(n,n') 93m Nb", Proceedings of FISA 2003, EU Research in reactor safety, http://www.cordis.lu/fp5-euratom/src/ev-fisa2003.htm, June 2004 P. Baeten, R. Soule, W. Assal, P. Chaussonnet, C. Destouches, C. Domergue, G. Imel, G.M. Thomas, D. Villamarin, E. Gonzalez-Romero, M. Plaschy, R. Chawla, JL. Kloosterman, Y. Rugama, A.A. Billebaud, R. Brissot, D. Heuer, M. Kerveno, C. Le Brun, E. Liatard, "Neutronic studies in support of accelerator driven www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 systems: the MUSE experiments in the MASURCA facility", Nuclear Science and Engineering, Vol. 148, Nr. 1, pp. 124-152, September 2004 D. Ruan, C. Kahraman, G. Buyukozkan, "A fuzzy heuristic multi-attribute conjunctive approach for ERP software selection", Proceedings of the 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, pp. 519-524, 1-3 September, 2004. D. Ruan, J. Ma, Y. Xu, "A model for semantic of linguistic information with incomparability", Proceedings of the 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, pp. 328-333, 1-3 September, 2004. D. Ruan, J. Ma, G. Chen, E.E. Kerre, "A method for association rules mining", The 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, pp. 173-178, 1-3 September, 2004. D. Ruan, Y. Xu, J. Liu, "Progress and prospect in lattice-valued logic systems based on lattice implication", The 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, pp. 28-34, 1-3 September, 2004. D. Ruan, T. Li, "An extended process model of knowledge discovery in database", Proceedings of the 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, pp. 185- 188, 1-3 September, 2004. D. Ruan, L. Martinez, J. Liu, "Fuzzy models to deal with heterogeneous information in decision making problems in engineering processes", Proceedings of the 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, pp. 266-271, 1-3 September, 2004. D. Ruan, "Fuzzy techniques in control and decision making for complex systems", Proceedings of the 12th Spanish Conference on Fuzzy Technologies and applications, Jaén, Spain, pp 9-14, 15-17 September, 2004 J. Heyse, C. Wagemans, K.W. Chou, L. De Smet, J. Wagemans, O. Serot, "High resolution measurements of the 234U(n,f) cross section", in proceedings of Seminar on Fission – Pont d'Oye V, Habay-la-Neuve, Belgium, 16-19 September 2003, Proceedings 2004, ISBN 981-238-792-7 O. Serot, C. Wagemans, J. Heyse, J. Wagemans, P. Geltenbort, "New results on the ternary fission of Cm and Cf isotopes", in proceedings of Seminar on Fission – Pont d'Oye V, Habay-la-Neuve, Belgium, 16-19 September 2003, Proceedings 2004, ISBN 981-238-792-7 V. Sobolev, "Modelling thermodynamic properties of dioxide fuels", Preprint of the article for the 11th Symposium on Thermodynamics of nuclear materials (STNM-11), P-29, Karlsruhe, Germany, November, 2004 D. Maes, "Design of the small scale eXperimental ADS: MYRRHA", in proceedings of Topical Day: From MYRRHA towards XT-ADS, Mol, Belgium, BLG-996, 23 November, 2004 V. Sobolev, E. Malambu, W. Haeck, Th. Aoust, MYRRHA-team, "Design of the MYRRHA sub-critical core", in proceedings of Topical Day: From MYRRHA towards XT-ADS, Mol, Belgium, BLG-996, 23 November, 2004 K. Van Tichelen, S. Van Genechten, D. De Bruyn, D. Maes, H. Aït Abderrahim, in proceedings of Topical Day: From MYRRHA towards XT-ADS, Mol, Belgium, BLG-996, 23 November, 2004 P. Schuurmans, MYRRHA-team, "The MYRRHA spallation loop", in proceedings of Topical Day: From MYRRHA towards XT-ADS, Mol, Belgium, BLG-996, 23 November, 2004 H. Aït Abderrahim, MYRRHA-team, "MYRRHA in the European frame", in proceedings of Topical Day: From MYRRHA towards XT-ADS, Mol, Belgium, BLG-996, 23 November, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Books D. Ruan, E.E. Kerre, C. Huang, "Fuzzy set theory and approximate reasoning", Wuhan University Press, Wuhan, China, 2004 (in Chinese) D. Ruan, X. Zeng, "Intelligent Sensory Evaluation - Methodologies and Applications", Springer, Heidelberg, Germany, March 2004 D. Ruan, G. Resconi, C. Kahraman. G. Büyüközkan, " Multidimentrional space of objects and features towards intelligent sensory fusion (chapter 2), Measuring software development value using fuzzy logic (chapter 16) in: Book: Intelligent Sensory Evaluation 2004 Springer", Springer Heidelberg, Germany, March 2004 D. Ruan, "Information Fusion and Decision-Making Under Uncertainties (the special issue of Int. J. of General Systems by Taylor & Francis)", Taylor & Francis, London, UK, April 2004 D. Ruan, "Applications of Intelligent Real-Time Systems for Nuclear Engineering", Kluwer, Dordrecht, The Netherlands, May 2004 D. Ruan, P. D'hondt, M. De Cock, M. Nachtegael, E. E. Kerre, Editors, "Applied Computational Intelligence", World Scientific, Proceedings of the 6th International FLINS Conference, Blankenberge, Belgium, September 1-3, 2004, ISBN 981-238-873-7 C. Wagemans, J. Wagemans, P. D'hondt, Editors, "Seminar on Fission – Pont d'Oye V", Castle of Pont d'Oye, Habay-la-Neuve, Belgium, 16-19 September 2003, World Scientific, Proceedings 2004, ISBN 981- 238-792-7 Presentations S. Heusdains, B. Arien, "MYRRHA relap model 50MW steady-state and transients", PDS-XADS project WP2.2 meeting, Lyon, France, 29-30 January 2004 D. Ruan, "Computational intelligence for safety-critical systems", Conference on methods and applications of knowledge discovery to support intelligent business decision – Bilateraal project China Vlaanderen, Hasselt, Belgium, 5-6 February, 2004 H. Aït Abderrahim, "PDS-XADS: WP5.3: General WP5.3 progress and other activities", PDS-XADS WP5.3 meeting, Genova, Italy, 17 March 2004 H. Aït Abderrahim, "Impact of P&T on waste management and geological disposal: impact of ADS on waste management", EURADWASTE'04, Luxembourg, 29 March-1 April, 2004. P. Baeten, H. Aït Abderrahim, P. D'hondt, B. Lance, P. Van Den Hende, D. Marloye, J. Basselier, "Critical Experiment with low-moderated mox rods in VENUS", The Need for Integral Critical Experiments with Low- moderated MOX Fuels, Workshop Paris, France, 14-15 April, 2004, ISBN 92-64-02078-0) N. Messaoudi, B.C. Na, "OECD/NEA International Benchmark on 3-D VENUS-2 MOX Core Measurements", PHYSOR 2004 – The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, USA, April 25-29, 2004 G. Van den Eynde, "The automatic computation of the discrete eigenvalues of the transport operator with anisotropic scattering", seminar at ULB, Brussels, belgium, 28 April, 2004 D. Ruan, " Nuclear reactor control with fuzzy logic approaches - strengths, weakness, opportunities, and threats", Enlarged Halden Programme Group Meeting, Sandefjord, Norway, May 9-14, 2004 G. Rimpault (CEA), S. Pillon (CEA), B. Giraud (FRAMATOME ANP), H. Aït Abderrahim, "ADS key issues for partitioning & transmutation", International conference on radiation shielding (ICRS-10) radiation protection and shielding (RPS-2004), Funchal, Madeira Island, Portugal, 9-14 May, 2004 H. Aït Abderrahim on behalf of ADOPT members, "The European ADS initiative present programme & perspectives", International conference on radiation shielding (ICRS-10) radiation protection and shielding (RPS-2004), Funchal, Madeira Island, Portugal, 9-14 May, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Th. Aoust, F. Vermeersch, "Shielding of the MYRRHA ADS", International conference on radiation shielding (ICRS-10) radiation protection and shielding (RPS-2004), Funchal, Madeira Island, Portugal, 9-14 May, 2004 H. Aït Abderrahim, A. Rolfe (OTL), S. Mills (OTL), S. Sanders (OTL), "MYRRHA, a Pb-Bi experimental ADS. Specific approach to radiation protection aspects in the project", International conference on radiation shielding (ICRS-10) radiation protection and shielding (RPS-2004), Funchal, Madeira Island, Portugal, 9-14 May, 2004 D. De Bruyn, "Ongoing activities in Belgium in the field of ads", IAEA Technical Meeting to "Review of National Programmes on Fast Reactors & Accelerator Driven Systems (ADS)"; Technical Working Group on Fast Reactors, Vienna, Austria, 10-14 May 2004 W. Haeck, H. Aït Abderrahim, C. Wagemans, "KEFF and KS burn up swing compensation in MYRRHA", OECD/NEA Fourth International Workshop on Utilization and Reliability of High Proton Power Accelerators, KAERI, Daejeon, Republic of Korea, 16-19 May 2004 K. Van Tichelen, P. Kupschus, H. Aït Abderrahim, F. Roelofs, E. Komen, "CFD analysis of the heavy liquid metal flow field in the MYRRHA pool", OECD/NEA Fourth International Workshop on Utilization and Reliability of High Proton Power Accelerators, KAERI, Daejeon, Republic of Korea, 16-19 May 2004 P. Schuurmans, P. Kupschus, A. Verstrepen, J. Cools, H. Aït Abderrahim, "The vacuum interface compatibility experiment (VICE) supporting the MYRRHA windowless target design", OECD/NEA Fourth International Workshop on Utilization and Reliability of High Proton Power Accelerators, KAERI, Daejeon, Republic of Korea, 16-19 May 2004 H. Aït Abderrahim, J. Pirson, K. Windey, E. Gonzalez, F. Alvarez Velarde, "MYRRHA: A multipurpose experimental ADS for R&D objectives.", 9th European Particle Accelerator Conference (EPAC '04), Lucerne (Switzerland), 5 - 9 July 2004 Th. Aoust, J. Cugnon, "Spallation reactions with neutron-rich and neutron-poor nuclei", EXON2004, International Symposium on Exotic Nuclei, Peterhof, Russia, 5 – 12 July 2004 D. Ruan, C. Kahraman, G. Buyukozkan, "A fuzzy heuristic multi-attribute conjunctive approach for ERP software selection", The 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, 1-3 September, 2004. D. Ruan, J. Ma, Y. Xu, "A model for semantic of linguistic information with incomparability", The 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, 1-3 September, 2004. D. Ruan, J. Ma, G. Chen, E.E. Kerre, "A method for association rules mining", The 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, 1-3 September, 2004. D. Ruan, L. Martinez, J. Liu, "Fuzzy models to deal with heterogeneous information in decision making problems in engineering processes", The 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, 1-3 September, 2004. D. Ruan, Y. Xu, J. Liu, "Progress and prospect in lattice-valued logic systems based on lattice implication", The 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, 1- 3 September, 2004. D. Ruan, T. Li, "An extended process model of knowledge discovery in database", The 6th International FLINS Conference on Applied Computational Intelligence, Blankenberge, Belgium, 1-3 September, 2004. V. Sobolev, "Modelling thermodynamic properties of dioxide fuels", 11th Symposium on Thermodynamics of nuclear materials (STNM-11), Karlsruhe, Germany, 6-9 September, 2004 D. Ruan, "Fuzzy techniques in control and decision making for complex systems", The 12th Spanish Conference on Fuzzy Technologies and applications, Jaén, Spain, 15-17 September, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 V. Sobolev, H. Aït Abderrahim, A. Al Mazouzi, M. Dierckx, D. Sapundjiev, P. Schuurmans, "SCK•CEN activities related to the LBE handbook", The 2nd meeting of the OECD/NEA WPCF working group on LBE technology, Paris, France, 23-24 September, 2004 D. Ruan, D. Maes, H. Aït Abderrahim, J. Liu, J-B Yang, "Cost Estimations for Large Scale Engineering Projects under Various Uncertainties- Case Study for the MYRRHA Machine with Intelligent Decision Systems", IAEA Technical Meeting on Increasing instrument calibration Interval through on-line monitoring technologies, Halden, Norway, 27-29 September, 2004 H. Aït Abderrahim, MYRRHA-team, "MYRRHA: A Multipurpose ADS for R&D, Need for New Nuclear Data?", ND2004, International Conference on Nuclear Data for Science and Technology, Santa Fé, USA 26 September – 1 October 2004 Th. Aoust, E. Malambu, H. Aït Abderrahim, "Importance of nuclear data for windowless spallation target design", ND2004, International Conference on Nuclear Data for Science and Technology, Santa Fé, USA 26 September – 1 October 2004 Th. Aoust, J. Cugnon, P. Henrotte, A. Boudard, S. Leray, C. Volant, "Recent progress of the Liège intranuclear cascade model", ND2004, International Conference on Nuclear Data for Science and Technology, Santa Fé, USA 26 September – 1 October 2004 H. Aït Abderrahim, D. De Bruyn, "Main WP5.3 Achievements, on behalf of PDS-XADS WP5.3 collaboration", PDS-XADS final meeting, Châlon sur Saône, France, 12-14 October 2004 H. Aït Abderrahim, "Monitoring and control of sub-critical systems and their implementation in an ADS", MUSE FP5 project, final meeting, Rome, Italy, 21-22 October, 2004 P. Baeten, "Reactivity monitoring in ADS", MUSE FP5 project, final meeting, Rome, Italy, 21-22 October, 2004 V. Sobolev, "Modelling thermodynamic properties of dioxide fuels", 11th Symposium on Thermodynamics of nuclear materials (STNM-11), Karlsruhe, Germany, 17-18 November, 2004. H. Aït Abderrahim, S. Lemehov, V. Sobolev, "Design and modelling of oxide fuel for incineration of americum and plutonium in an experimental ads", 8th Info Exchange Meeting on Actinides and Fission Products Partitioning and Transmutation, Las Vegas, USA, 9-11 November 2004 E. Malambu, W. Haeck, V. Sobolev, H. Aït Abderrahim, "MA and LLFP transmutation performance assessment in the MYRRHA small-scale ads", 8th Info Exchange Meeting on Actinides and Fission Products Partitioning and Transmutation, Las Vegas, USA, 9-11 November 2004 E. Malambu, B. Arien, "MYRRHA ADS safety analysis benchmark: Specifications, steady-state and transient calculations”, IAEA-Technical Meeting: CRP on “Studies of the Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste, HEFEI, China, November 21-26, 2004 D. Maes, "Design of the small scale eXperimental ADS: MYRRHA", Topical Day: From MYRRHA towards XT-ADS, Mol, Belgium, 23 November, 2004 V. Sobolev, E. Malambu, W. Haeck, Th. Aoust, MYRRHA-team, "Design of the MYRRHA sub-critical core", Topical Day: From MYRRHA towards XT-ADS, Mol, Belgium, 23 November, 2004 P. Schuurmans, MYRRHA-team, "The MYRRHA spallation loop", Topical Day: From MYRRHA towards XT-ADS, Mol, Belgium, 23 November, 2004 H. Aït Abderrahim, MYRRHA-team, "MYRRHA in the European frame", Topical Day: From MYRRHA towards XT-ADS, Mol, Belgium, 23 November, 2004 H. Aït Abderrahim, "ADS design needs for nuclear data and neutronics tools", IAEA technical meeting on "Application libraries for ADS and transmutation", IAEA headquarters, Vienna, Austria, 15-17 December, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Reports P. Baeten, "Experimental results of the irradiated BR3 MOX Configuration VENUS-REBUS", January 2004 N. Messaoudi, B.C. Na, "Benchmark on the 3-D VENUS-2 MOX core Measurements", NEA/NSC/DOC(2003)5, January 2004 D. De Bruyn, F. Vermeersch, "Reactor Vessel and Shielding Design of the Small-scale XADS: Sizing & Drawnings. Deliverable D27 of PDS-XADS project", FIKW-CT-2001-00179, March 2004 D. De Bruyn, "Building and Containment Design of the Small-scale XADS: Sizing & Drawnings. Deliverable D38 of PDS-XADS project", FIKW-CT-2001-00179, March 2004 V. Sobolev, E. Malambu, "Fuel rod, fuel assembly and sub-critical core of the experimental ads MYRRHA-II proposal for modifications in the reference design", Internal report IR-43, April 2004 J. Wagemans, J. Longhino, "Tango: neutron, dosimetry intercomparison", R-3894, June 2004 J. Wagemans, M. Willekens, L. Borms, J. Oeyen, "Reactor dosimetry with niobium revived at SCK•CEN", R-3883, June 2004 J. Wagemans, "Tango: neutron dosimetry results for the irradiations performed in the BR2 reactor", R- 3812-Rev(1), June 2004 W. Maschek et al. (FZK), P. Smith et al. (Serco Accurance), V. Sobolev, B. Arien, J. Wallenius (KTH), R. Konings (ITU), S. Pillon (CEA), "Safety Analysis for Accelerator Driven Transmuters (ADTs) with CERCER and CERMET Fuels. Deliverable 12 of FP5 FUTURE Project." R-4133, August , 2004. L. Borms, Y. Parthoens, A. Gys, "GERONIMO third campaign. Gamma spectroscopy PIE after ramp test on fuel segments GZR02, GZL33 and GZL32", R-3783, September 2004 E. Malambu, "Sub-critical core design of the small-scale XADS: sizing, drawings, fuel handling. Deliverable D12 – rev. 1 of PDS-XADS project", FIKW-CT-2001-00179, September 2004 J. Wagemans, "Nuclear power station Doel IV. Neutron dosimetry of surveillance capsule Doel IV/3", R- 3940, September 2004 P. Baeten, "Experimental results of the irradiated GKN UO2 Configuration", R-3941, October 2004 V. Sobolev, "Three variants of cooling of the MYRRHA reference core", Internal report TN-15, October 2004 V. Sobolev, N. Messaoudi, "About low enriched uranium use in the subcritical core of ads MYRRHA", Internal report TN-16, October 2004 L. Borms, Y. Parthoens, A. Gys, "REBUS PWR international programme gamma spectroscopy PIE on irradiated GKN II fuel rods", R-4047, November 2004 E. Lucon, J. Wagemans, M. Wéber, "Mechanical properties of Tihange III base and weld materials irradiated to high fluences", R-4049, November 2004 D. De Bruyn, H. Aït Abderrahim, B. Arien, D. Maes, "Technical option report on the small-scale LBE-cooled xads. Deliverable 61-appendix 1 of PDS-XADS project", FIKW-CT-2001-00179, December 2004 V. Sobolev, H. Aït Abderrahim, "Option of the initial enrichment of the MYRRHA core", Internal report TN- 14, December 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Expert Groups H. Aït Abderrahim, "Technical assessment of the IFMIF comprehensive design report (CDR)", European Fusion Development Agreement Close Support Unit (EFDA-CSU), ad hoc expert committee, 6-7 May, 2004 H. Aït Abderrahim, "Summary report of the expert group on application libraries for ADS and transmutation", IAEA headquarters, Vienna, Austria, 15-17 December, 2004 Training Courses S. Coenen, P. Baeten, "Reactorkinetica", Opleidingscentrum ELECTRABEL – SCALDIS, 2 March 2004, 28 May 2004 D. De Bruyn, "Designing underground structures: 20 years of experience at Mol", Course "Tunnels and underground constructions", UCL, Louvain-La-Neuve, 15 March 2004 H. Aït Abderrahim, "MYRRHA, a multipurpose ADS for R&D, status of the project at mid-2004", Colloque Département de Physique, UCL, Louvain-La-Neuve, 28 October 2004 D. De Bruyn, "Le dimensionnement du laboratoire souterrain à Mol", Course "Tunnels", UCL, Louvain-La- Neuve, 16 November 2004 D. De Bruyn, "Comportement thermo-hydro-mécanique de l'argile de Boom. L'influence d'une élévation de température sur son comportement physique et méchanique dans le cadre de la problématique de l'enfouissement des déchets radio-actifs", Course "Thermo-hydromécanique des matériaux", UCL, Louvain-La-Neuve, 16 November 2004 D. De Bruyn, "Le dimensionnement du laboratoire souterrain à Mol", Course "Constructions souterraines", ULB, Brussels, 8 December 2004 Conferences K. Van Tichelen, S. Van Genechten, D. De Bruyn, D. Maes, H. Aït Abderrahim, "Topical Day: From MYRRHA toward XT- ADS a European experimental ADS at Mol, Mol, Belgium, 23 November, 2004 Reactor Material Research Publications Y. Parthoens, V. Smolders, A. Gys, "Feasibility study of on-line digital X-ray imaging for irradiated fuel rods", European Working Group "Hot laboratories and remote handling". Proceedings of the plenary meeting 2003, held in Saclay, September 22-24 D. Terentyev, L. Malerba, "Diffusivity of solute atoms, matrix atoms and interstitial atoms in Fe-Cr alloys: a molecular dynamics study", Journal of Nuclear Materials, pp. 1161-1165, 2004 E. Lucon, "Irradiation resistance of Eurofer97 at 300 C up to 10 dpa", Journal of Nuclear Materials, Vol. 329-333, pp. 1113-116, presented at the 11th International Conference on Fusion Reactor materials (ICFRM-11), Kyoto, December 7-12 2003, 2004 D. Kulikov, L. Malerba, O. Khrushcheva, "Calculations of vacancy binding energies to Cu-V complexes in FeCu alloys", The Society of Photo-Otical Instrumentation Engineers,Vol. 5400, A.I. Melker Editor, SPIE Proceedings, 7th International Workshop on Nondestructive Testing and Computer Simulations in Science and Engineering, 2004 D. Terentyev, L. Malerba, P. Olsson, M. Hou, "Atomic scale modelling of chromium diffusion and melting point in alpha-iron and iron-chromium alloys, using high-temperature molecular dynamics simulation", The Society of Photo-Otical Instrumentation Engineers,Vol. 5400, A.I. Melker Editor, SPIE Proceedings, 7th International Workshop on Nondestructive Testing and Computer Simulations in Science and Engineering, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 C. Domain, C.S. Becquart, L. Malerba, "Simulation of radiation damage in Fe alloys: an object kinetic Monte Carlo approach", Journal of Nuclear Materials, Vol. 335, pp. 121-145, 2004 D. Kulikov, L. Malerba, M. Hou, "On the binding energies and configurations of vacandy and copper- vacancy clusters in Bcc iron: a computational study", Mechanical & Aerospace Eng. Dept., UCLA, 2004 - ISBN 0-9762064-1-2, Proceedings of the 2nd International Conference on Multiscale Materials Modelling, Ed. N.M. Ghoniem, Los Angeles, California, USA, October 11-15, 2004 C. Domain, C.S. Becquart, L. Malerba, "Kinetic Monte Carlo simulations of microstructural evolution in alfa- Fe under irradiation", Mechanical & Aerospace Eng. Dept., UCLA, 2004 - ISBN 0-9762064-1-2, Proceedings of the 2nd International Conference on Multiscale Materials Modelling, Ed. N.M. Ghoniem, Los Angeles, California, USA, October 11-15, 2004 K. Verheyen, A. Almazouzi, L. Malerba, C. Domain, J. Kuriplach, S. Van Petegem, "Precipitation-Induced hardening of thermally aged Fe-Cu alloys: a multiscale modelling stud and its experimental validation", Mechanical & Aerospace Eng. Dept., UCLA, 2004 - ISBN 0-9762064-1-2, Proceedings of the 2nd International Conference on Multiscale Materials Modelling, Ed. N.M. Ghoniem, Los Angeles, California, USA, October 11-15, 2004 A. Leenaers, S. Van den Berghe, E. Koonen, C. Jarousse, F. Huet, M. Trotabas, M. Boyard, S. Guillot, L. Sannen, M. Vewerft, "Post-irradiation examination of uranium-7 wt% molybdenum atomized dispersion fuel", Journal of Nuclear Materials,Vol. 335, pp.39-47, 2004 L. Malerba, D. Terentyev, "Molecular dynamics simulation of displacement cascades in Fe-Cr alloys", Journal of Nuclear Materials, Vol. 329-333, pp. 1156-1160, proceedings of 11th International Conference on Fusion Reactor materials (ICFRM-11), Kyoto, December 7-12, 2003, 2004 S. Lemehov, M. Verwerft, V. Sobolev, "Thermomechanical modeling of prototypic targets containing high concentrationsof minor actinides", Chapter 5, Editor 2004 D. Terentyev, L. Malerba, "Diffusivity of solute atoms, matrix atoms and interstitial atoms in Fe-Cr alloys: a molecular dynamics study", Journal of Nuclear Materials,Vol. 329-333, pp. 1161-1165, proceedings of 11th International Conference on Fusion Reactor materials (ICFRM-11), Kyoto, December 7-12, 2003, 2004 M. Vankeerberghen, "A mechanico-electrochemical diagram for crack growth under EAC conditions", NACE Corrosion/2004 Paper 04573, 2004 S. Van den Berghe, A. Leenaers, C. Ritter, "Antiferromagnetism in MUO3 (M = K, Rb) studied by neutron diffraction", Journal of Solid State Chemistry, Vol. 177, pp. 2231-2236, 2004 A. Leenaers, S. Van den Berghe, E. Koonen, P. Jacquet, C. Jarousse, B. Guigon , A. Ballagny, L. Sannen, "Microstructure of U3Si2 fuel plates submitted to a high heat flux", Journal of Nuclear Materials, Vol. 327, pp. 121-129, 2004. R.W. Bosch, B. Schepers, M. Vankeerberghen, "Development of a scratch test in an autoclave for the measurement of repassivation kinetics of stainless steel in high temperature high pressure water", Electrochemica Acta, Vol. 49, pp. 3029-3038, 2004 E. Lucon, R. Chaouadi, M. Decréton, "Mechanical properties of the European reference RAFM steel (EUROFER97) before and after irradiation at 300 C", Journal of Nuclear Materials, Vol. 329-333, pp.1078- 1082, 2004 M. Vankeerberghen, "Critical characteristic dimension or geometry for determining the susceptibility of a crevice to crevice corrosion", The Journal of science and engineering corrosion,Vol.60, No. 8, pp. 707-717, 2004 M. Vankeerberghen, "Will finite - element analysis find its way to the design against stress Corrosion cracking", 2nd International conference on Environment-Induced cracking of metals (EICM-2), 2004 E. Lucon, M. Scibetta, E. van Walle, "On the Possibility of avoiding the use of a clip gage when testing precracked charpy-V specimens in the ductile-to-brittle transition region", Journal of Testing and Evaluation,Vol.32 No. 4, pp.334-339, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 C. Domain, L. Malerba, G. Monnet, K. Verheyen, S. Jumel, J.C. van Duysen, "DUPAIR: a line tension moder for a first assessment and interpretation of radiation-induced hardening experiments", Mechanical & Aerospace Eng. Dept., UCLA, 2004 - ISBN 0-9762064-1-2, Proceedings of the 2nd International Conference on Multiscale Materials Modelling, Ed. N.M. Ghoniem, Los Angeles, California, USA, October 11-15, 2004 F. Soisson, A.V. Barashev, C. Becquart, M.J. Caturla, J. Dalla-Torre, C. Domain, L. Malerba, "Kinetic Monte Carlo Simulations of Microstructural Evolutions under Irradiation", UCLA, ISBN 0-9762064-1-2, p.551, Proceedings of the 2nd International Conference on Multiscale Modelling, Ed. N.M. Ghoniem, October 11-15, Los Angeles, California USA, 2004 J. Wallenius, I. A. Abrikosov, R. Chakarova, C. Lagerstedt, L. Malerba, P. Olsson, V. Pontikis, N. Sandberg, D. Terentyev, "Development of an EAM potential for simulation of radiation damage in Fe-Cr alloys", Journal of Nuclear Materials, Vol. 329-333, pp. 1175-1179, presented at 11th International Conference on Fusion Reactor materials (ICFRM-11), Kyoto, December 7-12, 2003, 2004 D. Terentyev, L. Malerba, Yu.N. Osetsky, A.V. Barashev, "Self-interstitial cluster diffusion in BCC Fe-Cr alloys: a molecular dynamics study", Mechanical & Aerospace Eng. Dept., UCLA, 2004 - ISBN 0-9762064- 1-2, Proceedings of the 2nd International Conference on Multiscale Materials Modelling, Ed. N.M. Ghoniem, Los Angeles, California, USA, October 11-15, 2004 R. Chaouadi, "An energy-based crack extension formulation for crack resistance characterization of ductile materials", Journal of Testing and Evaluation, Vol. 32, N°6, pp. 469-475, November 2004 M. Scibetta, J. Schuurmans, "Development and qualification of an algorithm for the development of the initial linear portion of a force versus displacement record", Journal of Testing and Evaluation, Vol. 32, N°6, pp.500-503, November 2004 M. Valo, E. Lucon, M. Brumovsky, L. Debarberis, J. Kohopää, F. Gillemot, "Fracture Mechanics based embrittlement (Frame)", Conclusion symposium on shared-cost and concerted actions FISA 2003 EU research in reactor safety, European Commission, 10-13 November 2003. A.A.F. Tavassoli, A. Alamo, L. Bedel, L. Forest, J.-M. Gentzbittel, J.W. Rensman, E. Diegele, R. Lindau, M. Schirra, R. Schmitt, H.C. Schneider, C. Petersen, A.-M. Lancha, P. Fernandez, G. Filacchioni, M. F. Maday, K. Mergia, N. Boukos, N. Baluc, P. Spätig, E. Alves, E. Lucon, " Materials design data for reduced activation martensitic steel type EUROFER", J. Nuclear Materials, vol. 329-333 (2004), pp. 257-262 (presented at the 11th International Conference on Fusion Reactor materials (ICFRM-11), Kyoto, December 7-12, 2003). R. Lindau, A. Möslang, M. Reith, M. Klimiankou, E. Morris, A. Alamo, F. Tavassoli, C. Cayron, A. Lancha, P. Fernandez, N. Baluc, R. Schaüblin, E. Diegele, J. Rensman, B. v.d. Schaaf, E. Lucon, W. Dietz, "Present development status of Eurofer and ODS for application in blanket concepts", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. Presentations A. Almazouzi, "Contribution to the physics modelling", IP-PERFECT Kick off meeting, Renardiéres France, January 19-20, 2004 A. Almazouzi, "Specification and fabricability of the material and its operation conditions", IP-Eurotrans preparatory meeting, Karlsruhe, January 21, 2004 S. Van Dyck, "EC FP5 project PRIS: SCK contribution in WP 2 and 5", PRIS semi annual project meeting, Arlanda, Sweden, February 17-18, 2004 A. Almazouzi, Ph. Benoit, "IP-EUROTRANS, DEMETRA WP3", Paris, February 18, 2004 A. Almazouzi, "Experimental validation of dislocation-obstacle interaction using internal friction", IP- PERFECT Meeting, Prague Ceck Republic, February 26-27, 2004 A. Almazouzi, "Quantative characterisation of the microstructure", IP-PERFECT Meeting, Prague Ceck Republic, February 26-27, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 E. Lucon, "Correlations between charpy impact data and fracture toughness results", FITNET Mid-Term Meeting, HGR, Brussels, March 2-3, 2004 A. Almazouzi, "Advanced experimental tools to characterise nuclear materials", BNEN seminar, Mol, March 9, 2004 S. Van den Berghe, A. Leenaers, B. Vos, L. Sannen, M. Verwerft, "Observation of a Duplex Zr-Cs-U-O Bonding layer in high power fuel", PCI-2004, Cadarache, March 9-11, 2004 E. van Walle, "TANGO: present status - research agreement BL/52/A01 within the bilateral cooperation Belgium-Argentina", Mol, March 19, 2004 A. Leenaers, S. Van den Berghe, E. Koonen, C. Jarousse, F. Huet, M. Trotabas, M. Boyard, S. Guillot, L. Sannen, M. Verwerft, " Post-irradiation observations on U-7wt% Mo atomised dispersion fuel", RRFM- 2004, Research Reactor Fuel Management Conference, Munich, March 22-24, 2004 S. Van den Berghe, A. Leenaers, E. Koonen, P.Jacquet, L. Sannen, C. Jarousse, B. Guigon, A. Ballagny, "Microstructure of U3SI2 fuel plates submitted to a high heat flux", RRFM-2004, Research Reactor Fuel Management Conference, Munich, March 22-24, 2004 A. De Bremaecker, L. Ayrault (CEA), "Experimental study of the interaction of boron carbide and oxidation products with materials under FPT3 representative conditions", Phebus Information meeting, Petten Netherlands, March 31, 2004 A. Almazouzi, "Material challenges for ADS MYRRHA", Internal Seminar, Mol, April 9, 2004 E. van Walle, "The Belgian Nuclear Research Centre SCK•CEN", IMR, Oarai, Japan, 13-14 April, 2004 L. Malerba, "Simulación computacional de daño por irradiación en materiales nucleares - Proyectos Europeos", Seminar, Argentina, April 22, 2004 S. Sapundjiev, E. Lucon, M. Matijasevic, S. Van Dyck, A. Almazouzi, "Synergetic effects between neutron irradiation and LME: Irradiation in BR2 at 200 C and PIE", MEGAPIE-TEST meeting, Brasimone, Italy, April 30, 2004 A. Almazouzi, "The Belgian Nuclear Research Center SCK•CEN and The Reactor Materials Research Department", Invited Seminar OCAS, Gent, May 10, 2004 E. Lucon, K. Wallin, M. Valo, "QA procedure for verifying the consistency of fracture toughness data: the EU project "FRAME"", ASTM E08.08.02, Washington, USA, May 10, 2004 S. Van Dyck, A. Almazouzi, "Post irradiation annealing study of the relationship between microstructure, mechanical properties and IASCC behaviour of stainless steel", Halden IASCC review meeting, Halden, May 12, 2004 E. Lucon, "TTMS-001a and TTMS-001b RAFM Steels - Irradiation Performance", WP 2005/06 Activities EFDA, Garching, May 12, 2004 M. Scibetta, S. Van Dyck, "Development and qualification of an algorithm for the determination of the initial linear portion of a force versus displacement record", ASTM E08.07 committee meeting, Salt Lake City, May 17-21, 2004 M. Scibetta, "Impact of the precracking requirements on economical considerations", ASTM E08.07 committee meeting, Salt Lake City, May 17-21, 2004 E. van Walle, R. Gérard, E. Lucon, R. Chaoaudi, M. Scibetta, "Direct fracture toughness evaluation of belgian RPV-surveillance", IAEA Symposium, Moscow, May 22-29, 2004 D. Sapundjiev, E. Lucon, M. Matijasevic, S. Van Dyck, A. Almazouzi, "Mechanical Behaviour of candidate steels in LBE after irradiation in BR2 at 200 C", 5th MEGAPIE technical meeting, Nantes France, May 25, 2004 A. Almazouzi, M. Matijasevic, "Status report on Deliverable 9 - Modelling oriented experiments on Fe-Cr-C model alloys", EFDA Follow-up Meeting, Villigen, June 22-23, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 L. Malerba, "Atomistic simulation of radiation damage in iron alloys and silicon carbide", Invited Seminar, Karlsruhe, June 24, 2004 L. Malerba, C. Domain, C. Becquart, D. Kulikov, "Kinetic Monte Carlo simulation of irradiation effects in bcc Fe-Cu alloys", 7th International Conference on simulation of radiation effects in solids, Helsinki, June 28 - July 2, 2004 A. Almazouzi, D. Terentyev, M. Matijasevic, L. Malerba, "On the understanding of irradiation damage accumulation in Fe-Cr alloys - Simulation versus experiments", SPIRE Meeting, Amsterdam, July 2, 2004 A. Rahier, S. Picaud, A. Darchen, "Electromechanical behaviour of U (IV) and U (VI) in phosphoric acid", Sixth international conference on nuclear and radiochemistry, 29 August to 3 September 2004, Aachen, Germany, August-September, 2004 L. Sannen, A. Gys, Y Parthoens, "Refabrication of fuel rodlets qualification of the end plug welds", HOTLAB Plenary Meeting, Halden, Norway, September 6-8, 2004 A. Pellettieri, M. Scibetta, P. Wouters, A. Leenaers, G. Verpoucke, "Design and fabrication of dead weight equipment to perform creep measurements on highly beryllium specimens", HOTLAB Plenary Meeting, Halden, Norway, September 6-8, 2004 R. W. Bosch, G. Nagy, D. Feron, M. Navas, W. Bogaerts, D. Kárnik, T. Dorsch, A. Molander, K. Mäkelä, "Results of the LIRES Round Robin test on high temperature reference electrondes for LWR applications", EUROCORR 2004, September 12, 2004 R. W. Bosch, "Corrosion rate measurements and data validation with the Electrochemical Frequency Modulation (EFM) technique", Studiekern Corrosie, Utrecht, 29 September 2004 A. Almazouzi, E. Lucon, "Nitrogen effect on the mechanical properties of nuclear materials: RPV - and F/M steels", High nitrogen steels, Ostend, September 29-22, 2004 E. van Walle, M. Scibetta, "The Belgo-Argentine collaboration on Atucha-I short Overview", AVN, Brussels, October 11, 2004 R. W. Bosch, G. Nagy, D. Feron, M. Navas, W. Bogaerts, D. Kárnik, T. Dorsch, A. Molander, K. Mäkelä, "Statuts of the LIRES-project (Development of Light Water Reactor Reference Electrodes): Results of the Round Robin test and irradiation experiments", International Conference of Nuclear Reactor Systems, San Francisco, October 11-14, 2004 D. Kulikov, L. Malerba, M. Hou, "On the binding energies and configurations of vacancy and copper- vacancy clusters in Bcc iron: a computational study", 2nd international conference on multiscale materials modelling, Los Angeles, California, USA, October 11-15, 2004 L. Malerba, C.S. Becquart, C. Domain, "Kinetic monte carlo simulations of microstructural evolution in alfa- Fe under irradiation", 2nd international conference on multiscale materials modelling, Los Angeles, California, USA, October 11-15, 2004 D. Terentyev, L. Malerba, Yu. N. Osetsky, A.V. Barashev, "Self-Interstitial cluster diffusion in BCC Fe-Cr Alloys: a molecular dynamics study", 2nd international conference on multiscale materials modelling, Los Angeles, California, USA, October 11-15, 2004 C. Domain, L. Malerba, G; Monnet, K. Verheyen, S. Jumel, J.C. Van Duysen, "DUPAIR: a line tension moder for a first assessment and interpretation of radiation-induced hardening experiments", 2nd international conference on multiscale materials modelling, Los Angeles, California, USA, October 11-15, 2004 F. Soisson, J.Dalla-Torre, A.V. Barashev, C. Becquart, M.J. Caturla, C. Domain, L. Malerba, "KMC simulations of microstructural evolutions under irradiation", 2nd International Conference on Multiscale Modelling, Los Angeles, California, USA, October 11-15, 2004 E. van Walle, "Reflections on Belgian Consortium Participation for the 2006-2008 program", Tractebel, Brussel, October 19, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 E. van Walle, M. Caro, "The Belgian-Argentine Collaboration in Nuclear Safety", Achievements of the Belgian-Argentine Scientific Cooperation in Nuclear Safety, Buenos Aires, Argentina, October 25, 2004 M. Scibetta, "Proposed extension of project agreement I: collaboration on monitoring radiation damage in support of future CNA-1 plant life management", Belgo-Argentine cooperation agreement, Buenos Aires, October 25-27, 2004 E. Lucon, K. Wallin, M. Valo, "FRAME project: QA procedure for assessing data consistency and identifying possible outliers", ATHENA Final Workshop, Rome, October 25-27, 2004 E. van Walle, M. Caro, D. Ciriani, E. Chomik, M. Scibetta, R. Chaouadi, E. Lucon, "Project Agreement I: collaboration on monitoring radiation damage in support of future CNA-1 plant life management", Belgo- Argentine collaboration agreement, CNEA, Buenos Aires, Argentina, October 26, 2004 A. De Bremaecker, L. Ayrault (CEA), "Experimental study of the interactions of B4C and its oxidation products with the Y2O3-stabilised zirconia of the shroud, in Phebus-FPT3 representative conditions", 10th Iternational QUENCH Workshop, Karlsruhe Germany, October 26-28, 2004 M. Scibetta, E. van Walle, "Recent SCK•CEN activities of relevance to the ISTC programme", ISTC-contact expert group on PLIM kick-off meeting, Rome, October 27-28, 2004 E. van Walle, M. Caro, D. Ciriani, E. Chomik, M. Scibetta, R. Chaouadi, E. Lucon, "The Belgo-Argentine collaboration on Atucha I short overview", Belgo-Argentine collaboration agreement, CNEA, Buenos Aires, Argentina, October 28, 2004 E. Lucon, J.L. Puzzolante, G. Roebben, A. Lamberty, "Impact characterization of sub-size charpy V-notch specimens prepared from full-size certified reference charpy V-notch test pieces", ASTM E28 second symposium on pendulum impact machines: procedures and specimens, Washington, USA, November 10, 2004 E. Lucon, R. Chaouadi, E. van Walle, "Different approaches for the verification of force values measured with instrumented charpy strikers", ASTM E28 second symposium on pendulum impact machines: procedures and specimens, Washington, USA, November 10, 2004 Y. Parthoens, L. Borms, A. Gys, L. Sannen, "REBUS PWR Non-destructive testing irradiated UO2 fuel rods – Gamma spectrometry – BU measurements", Rebus PWR 4th PCM, Brussels, Belgonucléaire, November 18, 2004 L. Sannen, A. Gys, Y. Parthoens, G. Verpoucke, W. Claes, "REBUS Refabrication of Fuel Rodlets", REBUS- PCM, Brussels, November 18-19, 2004 L.Sannen, "REBUS-BWR refabrication of fuel rodlets", REBUS-BWR PCM1, Brussels, November 19, 2004 D. Terentyev, L. Malerba, "Fe-Cr alloy: primary damage and interstitial diffusion", 5th Workshop on Fe Cr materials for fusion applications, Paris, November 25-28, 2004 Y. Parthoens, A. Gys, L. Borms, G. Cools, L. Sannen, "GERONIMO 3 – GZR03 Nin-destructive examinations bore and after ramp", Geronimo 4th Top Gun 3rd PCM, Belgonucléaire, Brussels, December 9-10, 2004 Y. Parthoens, A. Gys, G. Verpoucke, L. Sannen, "GERONIMO 3 – Fission Gas Release (FGR) before and after ramp", Geronimo 4th Top Gun 3rd PCM, Belgonucléaire, Brussels, December 9-10, 2004 A. De Bremaecker, "The ferritic ODS : origin and development, in Mol and abroad", Mol Belgium, Working meeting on ferritic alloys and steels, December 13, 2004 A. Almazouzi, "Current research activities in Europe in support of the Fusion & Myrrha (ADS) concept", Working meeting on ferritic alloys and steels, Mol, Belgium, December 13, 2004 D. Terentyev, L. Malerba, "Actual problems in multiscale modelling of radiation damage in Fe-Cr alloys", Seminar at University of Uppsala, devoted to modern problems of damage induced by neutron irradiation, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Reports D. Sapundjiev, "Static exposure tests in liquid Pb-Bi eutectic", BLG-970, January, 2004 A. Leenaers, S. Van den Berghe, "EDX Analysis of metallic particles", R-3810, January 2004 E. Lucon, R. Chaouadi, M. Scibetta, J.L. Puzzolante, E. van Walle, "Nuclear Power Station Almaraz Unit II Pressure Vessel Steel Surveillance Programme Test Report of the Fourth Surveillance Capsule (Capsule W)", R-3815, January, 2004 D. Sapundjiev, R.W. Bosch, "Liquid metal embrittlement (LME) of fusion materials in Pb-17Li", Part I: Literature review and design hot cell SSRT set-up, R-3819, January, 2004 M. Scibetta, "Literature survey on the characterization of reactor pressure vessel cladding", R-3823, January, 2004 S. Gavrilov, M. Vankeerberghen, "Numerical simulation of IASCC", Capita Selecta 2003, R-3841, January, 2004 E. Lucon, A. Almazouzi, "Mechanical Response to irradiation for three high-Cr martensitic steels (EM10, T91, HT9), Intermediate Report: 1st specimen batch (2,6 dpa)", BLG-973, February, 2004 M. Scibetta, J. Schuurmans, "Development and qualification of an algorithm for the determination of the initial linear portion of a force versus displacement record", Support for the development of standard test methods in particular for the ASTM E08.07 committee, BLG-976, February, 2004 E.Lucon, R. Chaouadi, M.Scibetta, E. van Walle, "Supplementary Mechanical Characterisation of the Base Materials (C1L/C2L) of the 5th Surveillance Capsule of the Tihange I Nuclear Power Station (TH I/5)", R- 3792, February, 2004 D. Ciriani, E. Chomik, M. Caro, R. Chaouadi, E. Lucon, M. Scibetta, E. van Walle, "Project Agreement I: Collaboration on monitoring radiation damage in support of future CNA-1 Plant Life Management", Status report on the Analysis of the TANGO Irradiation: Mechanical Tests and Initial Evaluation - Belgo- Argentinian Cooperation Agreement Nuclear Safety and Plant Life Management, R-3818, February, 2004 R. Chaouadi, M. Scibetta, E. Lucon, J.L. Puzzolante, E. van Walle, "Radiation embrittlement assessment of the Doel I-II weld", Convention 2002 Task 1.3 Confirmatory Research, R-3843, February, 2004 M. Scibetta, J. Schuurmans, "Development and qualification of an algorithm for the determination of the initial linear protion of a force versus displacement record", Support for the development of standard test methods in particular for the ASTM E08,07 committee. Submitted for publication in Journal of Testing and Evaluation, P-28, February, 2004 S. Van Dyck, "Metallographic and mechanical characterisation of LWR irradiated components - BWR control blade handle materials", PRIS project, work package 2, D3&D4, R-3829, March, 2004 S. Van Dyck, "Fracture resistance determination of LWR irradiated components - BWR contral blade handle materials", PRIS project, work package 5, R-3839, March, 2004 R.W. Bosch, M. Postler, V. Ignatova, S. Van Dyck, "The Influence of the corrosion potential on the oxide layers formed at stainless steel under PWR conditions", Some introductory results combining electrochemical and surface analytical techniques, R-3846, March, 2004 D. Sapundjiev, A. Almazouzi, S. Van Dyck, "Synergetic effects between neutron irradiation and LME: PIE tests in lead-bismuth eutectic", Part I: Tests on non-irradiated samples – TECLA, R-3847, March 2004 A. Almazouzi, E. Lucon, E. van Walle, "Collaboration between SCK•CEN and IMR on the characterization of RPV-related materials", Compilation of available information for materials supplied by SCK•CEN to IMR, R-3849, March, 2004 M. Scibetta, A. Pellettieri, P. Wouters, "Design and fabrication of a dead weight equipment to perform creep measurements on highly irradiated beryllium", Field: Tritium Breeding and Materials, Area: Breeding Blanket, Task: TW-2-TTBB 007a, Deliverable D11 Ref-11a, BLG-979, April, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 M. Scibetta, A. Pellettieri, P. Wouters, "Qualification of a dead weight equipment to perform creep measurements on highly irradiated beryllium", Field: Tritium Breeding and Materials, Area: Breeding Blanket, Task: TW-2-TTBB 007a, Deliverable D11 Ref-11c, BLG-980, April, 2004 E. Lucon, R. Chaouadi, M. Scibetta, J.L. Puzzolante, E. van Walle, "Nuclear power station Doel IV. Pressure vessel steel surveillance programme. Final test report of the third surveillance capsule (Doel IV/3)", R-3836, April, 2004 E. Lucon, M. Scibetta, R. Chaouadi, E. van Walle, "Mechanical properties of Tihange III base and weld materials irradiated to high fluences - Phase 1: Characterization of the unirradiated condition and preparation of the irradiation in BR2", Electrabel-Tractebel/SCK•CEN Convention 2003 - Task 1,2, R-3845, April, 2004 W. Van Renterghem, "The influence of the post weld heat treatment on the microstructure of a submerged- arc weld SG2", Conventie Electrabel-SCK•CEN 2003, R-3851, April, 2004 A. Leenaers, S. Van den Berghe, "Post-irradiation examination of U-7%Mo dispersed fuel -Irradiation Future UMo-1 in BR2 reactor", Microstructural examination of fuel plate U7MTBR06", R-3853, April 2004 S. Van Dyck, "Mechanical characterisation of the materials from the CORIOLIS irradiation campaign", R- 3854, April, 2004 A. Gys, L. Sannen, W. Van Renterghem, "Refabrication of irradiated PWR fuel rodlets Pre-qualification report", FNT 90 98 110, R-3855, April, 2004 E.Lucon,J.-L.Puzzolante, M. Scibetta, E. van Walle, "Tensile and hardness tests on the unirradiated base and weld materials of the cofrentes RPV", Offer n : 301103/ Order n : PP04-0980, R-3857, April, 2004 R. Chaouadi, "RADAMO - An experimental databank for investigating irradiation strengthening of RPV materials", Convention 2003 Task 1.1 Damage Modeling, R-3858, April, 2004 M. Caro, "Project Agreement I: Predicting the CNA-1 RPV Embrittllement: spectrum and dose-rate effects considerations for the TANGO experiment", Belgo-Argentinian Cooperation Agreement Nuclear Safety and plant life management, R-3859, April, 2004 E. Lucon, "Frracture toughness tests on unirradiated and irradiated model alloys and steels performed at SCK•CEN within the FRAME project", Fracture Mechanics based Ebrittlement - FRAME contract n FIKS- CT-2000-00101, R-3861, April, 2004 A. Leenaers, S. Van den Berghe, "Diffusion bonding of stainless steel - zirconium using HIP", Microstructual examination, I-37, April, 2004 D. Kulikov, L. Malerba, M. Hou, "On the binding energies of copper-vacancy complexes in iron-copper alloys: a computational study", Convention with ULB, BLG-956, May, 2004 K. Verheyen, M. Jardin, A. Almazouzi, "Positron annihilation spectroscopy technique", Data acquisition and analysis, BLG-982, May, 2004 A. Leenaers, S. Van den Berghe, L. Sannen, "Sample preparation of highly irradiated beryllium", Field: Tritium Breeding and Materials , Area: Breeding blanket, Task: TW2-TTBB-007a, Final report for deliverable D11, R-3862, June, 2004 E. Lucon, "Materials tested within the FRAME Project (Model Alloys and RPV Steels): Chemical composition and tensile properties", R-3867, June, 2004 Sven Van den Berghe; Ben Vos, "Analysis of grain size and morphology in 3 batches of UO2 powder", Contract information, R-3922, June, 2004 L. Malerba, D. Terentyev, "Analysis of displacement cascade library for the Fe-10 % Cr alloy: incascade clustering", BLG-985, July, 2004 A. Rahier, "Analytical determination of Si in ferritic low alloy steels", Intermediate report, R-3928, July, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 D. Sapundjiev, A. Al Mazouzi, S. Van Dyck, "Synergetic effects between neutron irradiation and LME: PIE tests in lead - bismuth eutectic", Part II : Tests on irradiated samples - Contract No. FIKW-CT-2000-00092 TECLA, R-3929, July, 2004 P. Van Bree, "Determination of Cu, Ni, Mn, Mo, Cr, Al in ferritic low alloy steels by ICP-MS", Intermediate report, R-3931, July, 2004 M.E. Hamon, "Recovery and recylcing of the mercury from a mercury trapping product used in mercury porosimetry", Université de Rennes, Academic Year 2003-2004, July, 2004 A. Rahier, "The hydrogen evolution reaction (HER)", Mechanisms and associated overvoltages in neutral and alkaline solutions, BLG-987, August, 2004 E. Lucon, K. Wallin, M. Valo, "FRAME Project: Quality Assurance Procedure for Identifying Outliers and Assessing the Consistency of Fracture Touhness Data Produced by Partner Labs", FRActure Mechanics Based Embrittlement - FRAME - Contract No FIKS-CT-2000-00101, R-3868, August, 2004 W. Van Renterghem, A. Leenaers, "The microstructure of Incoloy 800HT and cold worked AISI 304 stainless steel before irradiation", Conventie Electrabel-SCK•CEN 2004, R-3938, August, 2004 S. Van Dyck, "Crack Growth testing of Nickel base alloys: INCONEL 600 - results of the ICG Round- Robin", Convention Electrabel NV - SCK•CEN, programme 2002-2003, R-3959, August, 2004 M. Scibetta, "Fracture toughness testing: Impact of the precracking requirements on economical considerations", Support for the ASRM E08,08,03 committee, BLG-981, September, 2004 E. Lucon, A. Almazouzi, "Mechanical Response to Irradiation at 200 C for EM10, T91 and HT9 - Final report: specimens irradiated to 2.6 and 3.9 dpa", Project SPIRE, BLG-986, September, 2004 L. Borms, Y. Parthoens, A. Gys, "GERONIMO Third campaign - Gamma Spectroscopy PIE after ramp test on fuel segments GZR02, GZL33, GZL32 and GZR03", R-3783, September, 2004 E. Lucon, R. Chaouadi, J.L. Puzzolante, M. Scibetta, E. van Walle, "Nuclear Power Station Doel IV Pressure Vessel Steel Surveillance Programme Final Test Report of the Third Surveillance Capsule (Doel IV/3)", Revision 1, R-3836, September, 2004 M. Scibetta, E. Lucon, E. van Walle, "SCK•CEN contribution to the CUPRIVA project", , R-3937, September, 2004 M. Vankeerberghen, "A computational model of the metal-film-solution interface for stress corrosion crack initiation", Part I: Steady state film processes, TN-11, September, 2004 M. Matijasevic, K. Verheyen, W. Van Renterghem, A. Almazouzi, "Introduction to TEM observation of Ferritic material: theory and practice", , BLG-993, October, 2004 L.Malerba, A. Caro, F. Djurabekova, E. Lopasso, R. Pasianot, "Collaboration on modelling with CNEA - Status Report", DWTC Research Agreement BL/52/A01, R-4002, October, 2004 F. Djurabekova, L. Malerba, "Computational study of small copper-vacancy clusters in iron-copper alloys", DWTC Research Agreement BL/52/A01, R-4003, October, 2004 M. Scibetta, "Qualification of the Köco-Micromark reconstitution equipment", Convention Electrabel- SCK•CEN 2004, R-4006, November, 2004 E. Lucon, M. Scibetta, J. Schuurmans, "Qualification of fracture toughness measurements from C(T) specimens with displacements measured on the front face", Convention 2004, R-4018, November, 2004 S. Van Dyck, "Compatibility of Eurofer97 reduced activation ferretic martensitic steel with hydrogen and liquids", Stress corrosion cracking of neutron irradiated Eurofer97 in high temperature water, R-4020, October, 2004 A. Almazouzi, "Positron Annihilation measurements of cold worked stainless steel", Convention Electrabel- SCK•CEN - Corrosion, R-4041, October, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 M. Jardin, K. Verheyen, A. Almazouzi, T. Toyama, Y. Nagai, "Comparison between two positron annhiliation setups", IM/Japan versus RMO-SCK•CEN/Belgium, BLG-983, November, 2004 R. W. Bosch, "High Temperature Electrochemistry in Light Water Reactor's - Book of abstract", One-Day Seminar related to the EC-project LIRES, BLG-997, November, 2004 E. Lucon, R. Chaouadi, M. Scibetta, E. van Walle, "Supplementary mechanical characterization of the base and weld materials of the 3rd surveillance capsule of the Doel IV nuclear power station (DL IV/3)", R-3991, November, 2004 A. Gys, L Sannen, W. Claes, Y. Parthoens, G. Verpoucke, W. Vanrenterghem, S. Bodart, "REBUS, irradiated PWR fuel rodlets – Refabrication and characterization", R-4044, November 2004 A. Gys, L Sannen, Y. Parthoens, S. Van den Berghe, W. Vanrenterghem, G. Verpoucke, "REBUS, irradiated PWR fuel rodlets – Refabrication and characterization", R-4044, November 2004 L. Borms, Y. Parthoens, A. Gys, "REBUS PWR International Programme - Gamma Spectroscopy PIE Irradiated PWR fuel rodlets refabrication Weld Qualification", R-4045, November, 2004 E. Lucon, J. Wagemans, M. Wéber, "Mechanical Properties of Tihange III Base and Weld materials irradiated to high fluences Phase 2: irradiation on BR2 and neutron dosimetry", Convention Electrabel- SCK•CEN 2004, R-4049, November, 2004 W. Van Renterghem, "Dislocation density and precipitates of six iron model alloys", PERFECT CO 90 03 1687, I-0044, November, 2004 L. Malerba, A. Almazouzi, "Proceedings of the ITEM workshop on prediction of radiation damage in ferritic alloys", Synergy between multiscale modelling and modelling-oriented experiments, BLG-1000, December 2004 J. Schuurmans, M. Scibetta, "The development of software tools for tensile testing at SCK•CEN", An integrated software solution to perform tensile tests on an Instron test bench, analyse the test results and generate the final report, BLG-1004, December 2004 Y. Parthoens, A. Gys, L. Borms, L. Sannen, "PIE on U-7%Mo dispersed fuel – Irradiation Future-UMo-1 in BR2 reactor", NDE of fuel plate U7MTBR06, R-3840, December, 2004 E. Lucon, A. Leenaers, J.L. Puzzolante, A. Rahier, M. Scibetta, P. Van Bree, "Hardness Measurements, Microstructural investigation and chemical analyses on scoop samples machined from irradiated ferritic welds and adjacent plate material", R-4046, December 2004 E. Lucon, J.L. Puzzolante, A. Rahier, M. Scibetta, P. Van Bree, "Hardness Measurements, Chemical Analyses and Fracture Toughness Tests on Cylinderical Samples (slugs) Machinded from an Irradiated Ferritic Weld", R-4050, December 2004 W. Van Renterghem, M. Verwerft, "Corrosion tests on Zircaloy welds: end plugs of non-instrumented rods", I-0047, December 2004 Thesis Anthony Feuillet, "Fissuration par corrosion sous contrainte dde l'acier inoxydable 304 sensibilisé dans une solution de thiosulfate", Promotion 2002-2004 - Université Paul Sabatier de Toulouse, Thesis, June, 2004 Marius Pageaud, "Scratch test - repassivation kinetics of 304 stainless steel in high temperature, high pressure water with controlled additions of boron and lithium", Promotion 2002-2004 - Université Paul Sabatier de Toulouse, Thesis, June, 2004 Jarne Verpoorten, "Kinetics of low temperature oxidation of UO2: a GARD study", Academiejaar 2003-2004 - Universiteit Leuven, Thesis, June, 2004 Tom Wauters, "Ontwerpen van een meetbank voor niet destructief onderzoek in een “hot cell” (Design of a measuring bench for non-destructive research in a hot cell)", Academiejaar 2003-2004 - Hogeschool Antwerpen, Thesis, June, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 K. Govers, "Comportement du combustible nucléaire et des gaz de fission: aspects globaux et partiels", Année académique 2003-2004 - Université Libre de Bruxelles, Thesis, June, 2004 Kristof Mijnendonckx, "Constructie van een ultrasone microboormachine voor hotcell-gebruik", Academiejaar 2003-2004 - Hogeschool Limburg, Thesis, June, 2004 Mathieu Gibilaro, "Investigation of electrochemical reaction kinetics in an aqueous boric acid - lithium hydroxide solution at room temperature", Promotion 2002-2004 - Université Paul Sabatier de Toulouse, Thesis, June, 2004 Marc Lauwers, "Methodevalidatie van lengte- en diametermeting volgens ISO 17025", Academiejaar 2003- 2004 - Hogeschool Antwerpen, Thesis, June, 2004 Conferences Seminar on "High Temperature Electrochemistry in Light Water Reactors", Campus Library Arenberg, Leuven, Belgium, 30 November, 2004 Poster International Conference K. Verheyen, A. Almazouzi, L. Malerba, C. Domain, J. Kuriplach, S. Van Petegem, "Precipitation-induced hardening of thermally aged Fe-Cu alloys: A multiscale modelling study and its experimental validation", 2nd international conference on multiscale materials modelling, Los Angeles, California, USA, October 11- 15, 2004 D. Kulikov, L. Malerba, M. Hou, "Vacancy and vacancy-impurity cluster binding energies calculation by a coupled MC and MD quenching technique", 7th International Conference on simulation of radiation effects in solids, Helsinki, June 28 - July 2, 2004 C.S. Becquart, C. Domain, L. Malerba, M. Hou, "The influence of the internal displacement cascades structure on the growth of point defect clusters in radiation environment", 7th International Conference on simulation of radiation effects in solids, Helsinki, June 28 - July 2, 2004 M. Matijasevic, "Poster Session: Modellisation of irradiation effects: modelling oriented experiments on pure Fe-Cr-C alloys", International School on Radiation Effects in Solids, Sicily, Italy, July, 2004 D. Terentyev, L. Malerba, M. Hou, "In-cascade interstitial cluster formation in concentrated ferritic alloys with strong solute-interstitial interaction: a molecular dynamics study", 7th International Conference on simulation of radiation effects in solids, Helsinki, June 28 - July 2, 2004 D. Sapundjiev, E. Lucon, A. Al Mazouzi, S. Van Dyck, "MYRRHA ADS-candidate materials compatibility with lead bismuth before and after neutron irradiation", Actinide and Fission Product Partitioning and Transmutation, Eight Information Exchange Meeting, Las Vegas, Nevada, USA, 9-11 November, 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Radioactive Waste and Clean-up Division Scientific Output 2004 Contents Waste & Evacuation ...... 1 Valorisation ...... 7 Site Restoration ...... 8 Nuclear Chemistry and Services ...... 10 Waste & Evacuation Publications W. Bastiaens, F. Bernier, M. Buyens, M. Demarche, X.L. Li, J.-M. Linotte, J. Verstricht, "The connecting gallery. The extension of the HADES underground research facility at Mol, Belgium." EURIDICE REPORT 03-294, December 2003. B. Laenen, M. De Craen, "Eogenetic siderite as an indicator for fluctuations in sedimentation rate in the Oligocene Boom Clay Formation (Belgium).", Publ.: ELSEVIER, Sedimentary Geology 163 (2004) pp. 165 – 174. X. Sillen, J. Marivoet, W. Cool, P. de Preter, "Testing safety and performance indicators in an assessment of the long-term performance of the geological disposal of spent fuel in Boom Clay", Proceedings: ICEM '03: The 9th International Conference on Environmental Remediation and Radioactive Waste Management. (on CD, session 48). 2003. F. Mees, R. Swennen, M. Van Geet, P. Jacobs, "Applications of x-ray computed tomography in the geosciences", Geological Society special publication no. 215 (243p.) pp. 1 – 6, Geological Society, London, UK, 2003. M. Van Geet, D. Lagrou, R. Swennen, "Porosity measurements of sedimentary rocks by means of microfocus x-ray computed tomography ( CT)", Geological Society special publication no. 215 (243p.) pp. 51 – 60, Geological Society, London, UK, 2003. M. Van Geet, A. Vervoort, M. Wevers, R. Swennen, S. Roels, E. Sellers "Recent advances of X-ray CT and its applications for rock material.", X-ray CT for Geomaterials; Soils, Concrete, Rocks - Otani & Obara (eds.). Kumamoto, Japan, 2004. M. De Craen, M. Van Geet, L. Wang, M. Put, "High sulphate concentrations in squeezed Boom Clay pore water: evidence of oxidation of clay cores.", Physics and Chemistry of the Earth 29 (2004) pp. 91 - 103. ELSEVIER, Amsterdam, The Netherlands, 2004. C. Cachoir, K. Lemmens "Static dissolution of alpha-doped UO2 in Boom Clay conditions: Preliminary results." Conf. : Scientific Basis for Nuclear Waste Management, MRS 2003, Kalmar, Sweden, 15-18 June 2003. Proceedings : Mat. Res. Soc. Symp. Vol. 807, 2004, pp. 59 – 64. F. Rorif, E. Valcke, M.A. Glaus, "The effect of cellulose degradation products on the solubility and sorption of Pu and Am in alkaline-plume-affected and in unaffected Boom clay" Conf. : Scientific Basis for Nuclear Waste Management, MRS 2003, Kalmar, Sweden, 15-18 June 2003. Proceedings : Mat. Res. Soc. Symp. Vol. 807, 2004, pp. 633 – 638. B. Kursten, F. Druyts, " Pitting Studies Under Anoxic Conditions on Candidate Container Materials AISI 316L hMo and UHB 904L for The Disposal of HLW in Argillaceous Formations" Conf.: Scientific Basis for Nuclear Waste Management, MRS 2003, Kalmar, Sweden, 15-18 June 2003. Proceedings: Mat. Res. Soc. Symp. Vol. 807, 2004, pp. 495 – 503. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 W. Bastiaens, M. Demarche, "The extension of URF HADES: realization & observations" Conf.: Waste Management 2003 (WM'03), Tucson, Arizona, 23-27 February, 2003. Proceedings: WM'03 Conference. J. Marivoet, "The role of hydrology in radioactive waste disposal systems." Proceedings: Water Stories, workshop held on occasion of the retirement of Prof.em. Dr. ir. André Van der Beken, Brussels, 30 September 2004. pp. 59 – 63. N. Maes, G. Delécaut, P. De Cannière, L. Wang, "Effect of reducing agents on the uranium concentration above uranium (IV) amorphous precipitate in Boom Clay pore water." Pub.: Radiochim. acta 92, 545-550 (2004). Presentations F. Druyts, E. Alves, C.H. Wu, "Methods for the mitigation of the chemical reactivity of Beryllium in steam." Conf.: 6th International Beryllium Workshop, Tokyo, Japan, 1–6 December 2003. F. Druyts, D. Mallants, X. Sillen, P. Van Iseghem, "Belgian Research on Fusion Beryllium Waste." Conf.: 6th International Beryllium Workshop, Tokyo, Japan, 1–6 December 2003. J. Marivoet, S. Voinis, P. Lalieux, P. De Preter, "Functions of Argillaceous Media in Deep Geological Disposal and their Handling in a Safety Case." Conf. : NEA Workshop Geosphere Stability, Braunschweig, Germany, 9–11 December 2003. M. Van Geet, I. Deniau, C. Largeau, C. Bruggeman, A. Maes, A. Dierckx, "Presence and evolution of natural organic matter in the Boom Clay" Conf. : NEA Workshop Geosphere Stability, Braunschweig, Germany, 9–11 December 2003. D. Mallants, "Evaluation of Gas Generation on Repository Performance in Case of Deep Disposal of LLW & Post-closure performance assessment for surface disposal of LLW containing inorganic non- radiological components." Training course: IAEA training course in the framework of the TC with Slovenia Performance assessment for low-level waste disposal, Mol, 22-27 March 2004. E. Valcke, S. Smets, S. Labat, P. Van Iseghem, N. Godon, P. Jollivet, N. Jockwer, K. Wieczorek, "CORALUS : An integrated in situ corrosion test on alpha-active HLW glass. (Poster)" Conf.: Euradwaste 2004, Luxembourg, 29–31 March 2004. G. Volckaert, F. Bernier, X. Sillen, M. Van Geet,J.-C. Mayor, I. Göbel, P. Blümling,B. Frieg, K. Su, "Similarities and Differences in the Behaviour of Plastic and Indurated Clays" Conf.: Euradwaste 2004, Luxembourg, 29–31 March 2004. B. Kursten, "Corrosion Evaluation of Metallic Materials for Long-Lived HLW/Spent Fuel Disposal Containers – review of 15-20 years of research." Conf.: Euradwaste 2004, Luxemburg, 29-31 March 2004. M. Van Geet, W. Bastiaens, G. Volckaert, M.V. Villar, M. Mingarro, A. Gens, B. Vallejan, M. Carron- charles, C. Imbert, F. Plas, "The RESEAL project. A large scale in situ demonstration test for repository sealing in an argillaceous host rock" Conf.: Euradwaste 2004, Luxemburg, 29-31 March 2004. P. Van Iseghem, "GLAMOR. A Critical Evaluation of the Dissolution Mechanisms of High-Level Waste Glasses in Conditions of Relevance for Geological Disposal." Conf.: MRS 2004, San Francisco, 13-16 April 2004. C. Cachoir, K. Lemmens "Dissolution tests with alpha-doped UO2 in Boom Clay conditions: results from static and dynamic tests." Conf. : Spent fuel workshop 2004, Chicago, 19-21 April 2004. D. Jacques, P. Seuntjens, J. Simunek, D. Mallants, M. Th. Van Genuchten, "Effect of increased salt concentration on cadmium leaching in acid sandy soils." Conf.: EGU first General assembly 2004, Nice, France, 25-30 April 2004. Pub.: Geophysical Research Abstracts, Vol. 6, 02979, 2004. D. Jacques, J. Simunek, D. Mallants, M. Th. Van Genuchten, "Reactive transport modelling in the www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 vadose zone with coupled PHREEQC – HYDRUS1D code." Conf.: EGU first General assembly 2004, Nice, France, 25-30 April 2004. Pub.: Geophysical Research Abstracts, Vol. 6, 02940, 2004. D. Mallants, N. Maes, D. Jacques, I. Thys, E. Smolders, H. Vandenhove, L. Diels, "Laboratory testing of uranium removal efficiency of reactive media for use in groundwater remediation. (Poster)" Conf.: EGU first General assembly 2004, Nice, France, 25-30 April 2004. Pub.: Geophysical Research Abstracts, Vol. 6, 07381, 2004. D. Mallants, H. Vandenhove, "Modelling radionuclide and heavy metal mobility in uranium mill tailings in Kyrgystan." Conf.: Subsurface radionuclide migration-Case studies organized by ITC School of underground waste storage and disposal & EAWAG Swiss Federal Institute for Environmental Science and Technology, Meiringen, Switzerland, 5-7 May 2004. D. Jacques, J. Simunek, D. Mallants, M. Th. Van Genuchten, "A general code to model multicomponent reactive transport for variably-saturated porous media." Conf.: The Third International Conference "Interfaces against pollution", Jülich, Germany, 24-27 May 2004. D. Jacques, K. Lemmens, P. Van Iseghem, "Geochemical modelling of SON68 and SM539 glass dissolution and gel formation at different temperatures using a solid solution model." Conf.: Goldschmidt Conference, Copenhagen, Danmark, 5-11 June 2004. P. Van Iseghem, N. Maes, M. Van Geet, L. Wang, M. De Craen, H. Moors, P. De Canniere, D. Jacques, K. Lemmens, C. Cachoir, S. Salah, "The role of Geochemistry in the research on geological disposal of high-level radioactive waste in a deep Boom Clay in Belgium." Conf.: Goldschmidt Conference, Copenhagen, Danmark, 5-11 June 2004. D. Jacques, J. Simunek, D. Mallants, P. Seuntjens, M. Th. Van Genuchten, "Geochemical coupled transport code for variably saturated flow conditions: Metal leaching in a podzol." Conf.: Goldschmidt Conference, Copenhagen, Danmark, 5-11 June 2004. F. Rorif, J. Fuger, J.F. Desreux, "Thermochemistry of selected sodium neptunyl carbonates. (Poster)" Conf.: The Sixth International Conference on Nuclear and Radiochemistry (NRC6), Aachen, Germany, 29August – 03 September 2004. D. Jacques, S. Oswald, T. Roose, A. Schenpf, P. Seuntjens, W. Van-Beinum, F. Gérard, G. Kirk, H. Nietfeld, B. Jaillard, "Validation of coupled speciation-transport models to describe root-uptake." Conf.: Rhizosphere 2004, Perspectives and Challenges - A tribute to Lorenz Hiltner, 2004, Munich, Germany, 12-17 September. J. Marivoet, "Disposal of high level radioactive waste in clay formations: the role of the geology for the long term safety" Conf.: UGV Symposium: Underground waste Disposal. Utrecht, The Netherlands 24 September 2004. J. Marivoet, "The role of hydrology in radioactive waste disposal systems." Conf.: Emiraat Prof. André Van der Beken, VUB, Brussels, Belgium, 30 September 2004. D. Mallants, "Performance/safety assessment studies for disposal of LILW/HLW." Training course: Cursus PA in het kader van de MEZ bilaterale samenwerking met Oosteuropa, SCK Mol, 27 September – 1 October 2004. D. Mallants, "Fundamentals of chemical transport: basic equations and parameters." Training course: Cursus PA in het kader van de MEZ bilaterale samenwerking met Oosteuropa, SCK Mol, 27 September – 1 October 2004. D. Mallants, "LLW management in Belgium" Conf.: A two-day trade mission was held in Bucharest, organised by BCE Network v.z.w. BCE Network (Central and Eeast European Network) is an interface between government and the (Flemish) private sector, providing a platform for companies interested in Central and Eastern Europe development, in light of the EU enlargement. BCE focuses on four sectors: “Environment”, “Economic and Regional Development”, “Transport and Infrastructure”, and “Culture”. Romania, 7-8 October 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 D. Jacques, J. Simunek, M. Th. Van Genuchten, M. Schaap, E.D. Mattson, "Recent Development in the Hydrus Software: Overland Flow and Biogeochemical Modules." Conf.: SAHRA 4th Annual meeting, Albuquerque, New Mexico, 13 – 15 October 2004. A. Sneyers, "The integrated project NF-PRO. Objectives, scope and project structure." Conf.: Meeting of the FP6 consultative committee Euratom - Fission, Brussels, 21 October 2004. D. Mallants, "Gas generation and potential impact on repository performance." Conf.: EURIDICE- SCK•CEN-NIRAS/ONDRAF Information Exchange meeting bituminised waste, Mol, 26 October 2004. E. Valcke, R. Gens, F. Rorif, A. Sneyers, P. Van Iseghem, "The effect of radiolytic and chemical degradation products." Conf.: EURIDICE-SCK•CEN-NIRAS/ONDRAF Information Exchange meeting bituminised waste, Mol, 26 October 2004. E. Valcke, X. Li, E. Weetjens, H. Moors, F. Bernier, P. De Canniere, J. Marivoet, L. Ortiz, F. Rorif, X. Sillen, A. Sneyers, M. Van Geet, P. Van Iseghem, G. Volckaert, A. Dierckx, R. Gens, H. Van Humbeeck, "Processes related to the uptake of water and release of NaNO3 by Eurobitum." Conf.: EURIDICE-SCK•CEN-NIRAS/ONDRAF Information Exchange meeting bituminised waste, Mol, 26 October 2004. F. Rorif, E. Valcke, "Evolution of the characteristics of the Eurobitum matrix." Conf.: EURIDICE- SCK•CEN-NIRAS/ONDRAF Information Exchange meeting bituminised waste, Mol, 26 October 2004. G. Volckart, F. Bernier, M. Demarche, P. Lalieux, "The construction and the experimental programme of the URF HADES at Mol, Belgium." Conf.: International workshop on Honoronobe underground research laboratory project, Tokyo, 27 October 2004. M. De Craen, "Site characterisation in plastic clays: specific example of the Boom Clay" Training course: Methodology for geological disposal. The fundamentals of geological disposal, Meiringen, 23- 26 November 2004. Reports M. Mazurek, F. Joe Pearson, G. Volckaert, H. Bock, "Features, Events and Processes Evaluation Catalogue for Argillaceous Media." NEA-4437, OECD 2003. J. Alonso (Coordinator), D.A. Becker, R. Storck, F. Besnus, D. Pellegrini, C. Serres, L. Johnson, J. Hart, J. Marivoet, X. Sillen, T. Vieno, H. Nordman, B. Petkovsek, "Bentonite barriers in integrated performance assessment (Benipa). Final report." Contract No FIKW-CT-2000-00015. EUR-21023, 2004. N. Maes, L. Wang, G. Delécault, T. Beauwens, M. Van Geet, M. Put, E. Weetjens, J. Marivoet, J. Van der Lee, P. Warwick, A. Hall, G. Walker, A. Maes, C. Bruggeman, D. Bennett, T. Hicks, J. Higgo, D. Galson, "Migration Case Study : Transport of radionuclides in a Reducing Clay Sediment (TRANCOM 2)" Contract No FIKW-CT-2000-00008. EUR-21022, 2004. M. Van Geet, N. Maes, W. Bastiaens, H. Moors, G. Volckaert, M. Put, F. Plas, C. Imbert, M. Carron- Charles, P. Maugis, M.V. Villar, M. Mingarro, M. Garcia-Gutierrez, A. Gens, B. Vallejan, “A large scale in situ demonstration test for repository sealing in an argillaceous host rock - phase 2 - RESEAL 2”, 5th Euratom framework programme 1998-2002. Key Action: Nuclear Fission. EC contract : FIKW-CT2000- 00010, 3rd scientific report, September 2002 – August 2003. R-3821, January 2004. M. Van Geet, N. Maes, W. Bastiaens, H. Moors, G. Volckaert, M. Put, F. Plas, C. Imbert, M. Carron- Charles, P. Maugis, M.V. Villar, M. Mingarro, M. Garcia-Gutierrez, A. Gens, B. Vallejan, “A large scale in situ demonstration test for repository sealing in an argillaceous host rock - phase 2 - RESEAL 2”, EC contract : FIKW-CT2000-00010, 6th management report, March 2003 - September 2003. R-3822, January 2004. P. Borgermans, "SOMOS - Safety and Operational Monitoring of nuclear waste repositories with fibre Optic sensing Systems." MID TERM REPORT. Reporting period: From 2001-12-01 to 2003-05-31. Contract N° : FIKW-CT2001-00190. R-3824, October 2003. A. Sneyers, G. Volckaert, "Regulatory framework and procedures for quality control and waste acceptance applicable to conditioned radioactive waste repatriated from foreign reprocessing facilities www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 to Belgium." Consultant report drafted on request by the Mitsubishi Corporation in the framework of contract RWMC FY2003. R-3805, December 2003. D. Mallants, G. Volckaert, S. Labat, "Parameter values used in the performance assessment of the disposal of low level radioactive waste at the nuclear zone Mol-Dessel. Volume 1, 2 and 3" Contract with NIRAS/ONDRAF KNT 90.00.1371. R-3521rev.1, December 2003. L. Hardy, D. Mallants, G. Volckaert, "Hydrogeological model for the safety evaluation: groundwater flow and transport calculations for the nuclear zone Mol-Dessel. Surface disposal of category A waste." Report to NIRAS/ONDRAF contract KNT 90.00.1371.01 R-3550rev.1, December 2003. V. Moise, P. Van Iseghem, "General Overview of Mixed Waste. Addressing performance assessment studies on the Belgian waste types."General Report I-34, January 2004. D. Mallants, A. Dierckx, G. Volckaert, L. Wang, T. Zeevaert, "Impact assessment of the radium storage facility of Umicore at the Olen site. Part 1: Safety data and migration study. + Appendices." Contractnr.: E023017. R-3478, January 2004. M. Gedeon, D. Mallants, "Hydrogeological model for the safety evaluation. Groundwater flow and transport calculations for the nuclear zone Mol-Dessel. Surface disposal of category A waste." Restricted Contract Report. Contract CO.90.00.1371.03. R-3797, January 2004. P. Meynendonckx, A. Sneyers, "The HADES Underground Research Facility Information brochures on the HADES URF." RWMC FY2003 Consultation 1 Task 2 Special Report 5. R-3825, January 2004. J. Verstricht, "IAEA Expert Group on Safeguards for Final Disposal of Spent Fuel in Geological Repositories." Belgian Contribution. IAEA Task JNT C 01273 BEL. R-3838, February 2004. L. Ortiz, "Utilization of HADES URF for other purposes than for R&D on radioactive waste disposal." RWMC FY2003 Consultation 1 Task 2 Special Report 2.5.2. R-3830, February 2004. A. Sneyers, "Report on the use FAQs for public information purposes." RWMC FY2003 Consultation 1 Task 2 Special Report 2.8. R-3835, February 2004. D. Mallants, J. Diederik, T. Zeevaert, "Evaluatie van de mogelijke impact van de berging van zeer laagactief afval aan de oppervlakte in de nabijheid van de D1-stortplaats van UMICORE-OLEN" Contract to NIRAS/ONDRAF CO 90.02.1633.00. DISCLAIMER : This report was prepared on behalf of NIRAS. The viewpoints presented and conclusions reached are those of the autor(s) and do not necessarily represent those of NIRAS, or any other party involved in the BRAEM project. R-3772, March 2004. F. Druyts, "Corrosion of fusion-specific waste material in a clay geological repository. Status report for the year 2003." Contract 90-02-1646-07 UT-BER. R-3848, March 2004. G. Volckaert, "Radiological impact assessment for human intrusion scenarios. Surface disposal of category A waste." Contract NIRAS/ONDRAF KNT.90.00.1371.04. R-3769, March 2004. D. Mallants, G. Volckaert, "Gedetailleerde beschrijving van het bergingssysteem en zijn omgeving. Veiligheidsstudies voor berging van radioactief afval van categorie A" Report to NIRAS/ONDRAF Contract KNT 90 98 1073. R-3321rev.2, April 2004. X. Li, F. Bernier, "Characterisation and compatibility with the disposal medium of Eurochemic reprocessing waste forms Interaction swelling bitumen – host rock: Scoping calculations." Work performed in the frame of EUROCOMPAT, Task BV6 (RP.WD.027, WP3) of Annex 2 of NIRAS/ONDRAF contract CCHO-90/123-2. R-3852, April 2004. A. Sneyers, G. Volckaert, "Waste management of ILW and HLW related to geological disposal." RWMC FY2003 Consultation 1 Task 2 Special Report 2.1. R-3831, May 2004. A. Sneyers, G. Volckaert, "Overview of organisations in Belgium producing radioactive waste." RWMC FY2003 Consultation 1 Task 2 Special Report 2.3. R-3832, May 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 A. Sneyers, G. Volckaert, "Status of disposal of LLW, ILW and HLW in Belgium." RWMC FY2003 Consultation 1 Task 2 Special Report 2.4. R-3833, May 2004. L. Ortiz, "Summary information on the Belgian R&D programme on geological disposal." RWMC FY2003 Consultation 1 Task 2 Special Report 2.6. R-3828, May 2004. A. Sneyers, G. Volckaert, "Report on the institutional framework and the role of the implementing organisation NIRAS/ONDRAF applicable to radioactive waste management in Belgium." RWMC FY2003 Consultation 1 Task 2 Special Report 2.7. R-3834, May 2004. D. Mallants, D. Jacques, "Performance Assessment for Deep Disposal of Low and Intermediate Level Short-Lived Radioactive Waste in Boom Clay. Geological disposal of category A waste." Contract to NIRAS/ONDRAF KNT.90.98.1072.01. R-3793, May 2004. M. Van Geet, "Characterisation of Boom Clay organic matter: mobile and immobile fraction. Interim report for the period 2001-2003." D.S. 2.82. R-3884, June 2004. M. Van Geet, N. Maes, W. Bastiaens, H. Moors, G. Volckaert, M. Put, F. Plas, C. Imbert, M. Carron- Charles, P. Maugis, M.V. Villar, M. Mingarro, M. Garcia-Gutierrez, A. Gens, B. Vallejan, “A large scale in situ demonstration test for repository sealing in an argillaceous host rock - phase 2 - RESEAL 2”, EC contract : FIKW-CT2000-00010, 7th management report, September 2003 – February 2004. R- 3903, June 2004. D. Mallants, "Special report on the status of the LLW programme in Belgium." Consultant report drafted on request by the Mitsubishi Corporation in the framework of contract RWMC FY2003 Consultation 1 Task 2 Special Report 2, R-3809, June 2004. I. Wemaere, J. Marivoet,S. Labat,T. Maes, R. Beaufays, "Zoersel borehole of the hydro/96neb campaign: technical aspects and hydrogeological investigations. Geological disposal of conditioned high-level and long-lived radioactive waste." Contractnr: CO 90 98 1685.00, R-3892, June 2004. M. De Craen, L. Wang, E. Weetjens, "Natural evidence on the long-term behaviour of trace elements and radionuclides in the Boom Clay." Final report of DS 2.9 for the period 2000-2003. Contract NIRAS: CCHO 2000-773/00/00, KNT 90 01 1467. R-3926, July 2004. I. Wemaere, J. Marivoet, S. Labat,T. Maes, R. Beaufays, "Rijkevorsel borehole of the hydro/96neb campaign: technical aspects and hydrogeological investigations. Geological disposal of conditioned high-level and long-lived radioactive waste." Contractnr: CO 90 98 1044.05, R-3930, September 2004. M. De Craen, L. Wang, M. Van Geet, H. Moors, "Geochemistry of Boom Clay Pore Water at the Mol site – status 2004" BLG-990, September 2004. N. Maes, L. Wang, G. Delécault, T. Beauwens, M. Van Geet, M. Put, E. Weetjens, J. Marivoet, J. Van der Lee, P. Warwick, A. Hall, G. Walker, A. Maes, C. Bruggeman, D. Bennett, T. Hicks, J. Higgo, D. Galson, "Migration Case Study : Transport of radionuclides in a Reducing Clay Sediment (TRANCOM 2)" Final Scientific and Technical report of the EC TRANCOM-2 project. BLG-988, September 2004. L. Wang, P. De Cannière, D. Jacques, H. Moors, M. Van Gompel, M. Aertsens, "Experimental and modelling studies of Boom Clay exposed to an alkaline perturbation." Final Report to NIRAS/ONDRAF, DS 2.13 (2002-2003). Contract CO-90 01 1467.05, R-4019, September 2004. M. Aertsens, N. Maes, K. Lemmens, "Characterization and compatibility with the disposal medium of Cogema and Eurochemic reprocessing waste forms. Silica retention in Boom Clay, FoCa clay and M2. Thematical report for WP1.exp3 of RP.WD.008 for the period January 2000 - June 2003" Tasks VM-6 and GV8 of NIRAS/ONDRAF contracts N° CCHO-90/123-1 and CCHO-90/123-2 (vitrified waste), R- 3866, September 2004. F. Druyts, "Interaction of Be12Ti with air and steam at HCPB BB relevant temperatures. Interim report on the results in air." SCK contract CO-90-02-1646-13, R-4038, October 2004. F. Druyts, "Chemical reactivity of dust and flakes and D mobilisation experiments from co-deposited layers – Reactivity of Be, W, Mo, and CFC." Final report for ITER Task TW0-T438/06, R-4039, October 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 D. Mallants, "Acceptability of beryllium waste in near surface waste disposal sites." Final report of Task TW1-TSW-002-D6, R-4043, November 2004. D. Mallants, E. Weetjens, L. Wang, "Evaluation of the consequences of inorganic non-radiological components in case of subsurface disposal of low and intermediate level short-lived radioactive waste at the nuclear zone of Fleurus-Farciennes. Geological disposal of category A waste." Contract to NIRAS/ONDRAF KNT.90.02.1620.00. R-3782, November 2004. A. Sneyers, G. Volckaert, "Information update concerning geological disposal programme in Belgium." RWMC FY2003 Consultation 1. R-3837, November 2004. J. Marivoet, "A Study on Upgrading Safety Assessment Technology." Case Survey of Handling of Uncertainties in Data, Models and Scenarios for Safety Assessment (Belgium) RWMC FY2004 Consultation 1. R-4058, December 2004. Valorisation Publications L. Denissen, V. Massaut - IRDIT project: Innovative Remote Dismantling Techniques – Remotely controlled water jet cutting tool used in a small PWR (BR3) (052/04-02) Euradwaste, Luxemburg 29-31 March 2004 L. Denissen, L. Ooms, H. Davain - Remote high pressure water jet cutting used at the BR3 nuclear dismantling site (052/04-03). 17th International Conference on Water Jetting, Advances and Future needs, Mainz, Germany, 7-9 September, 2004 V. Massaut, G. Collard - R&D techniques and how to continuously improve them (052/04-04) NEA International Workshop: Safe, efficient and cost-effective decommissioning Rome, 6-10 September 2004 I. Verwaest - The material (and waste) management in NPP decommissioning: a practical example and return of experience (052/04-07) IAEA International symposium on the Disposal of Low-Activity Radioactive Waste, Cordoba, Spain, 13-17 September 2004 Presentations V. Massaut - Is dismantling an exciting job? Internal Lunch Talk, SCK•CEN, 26 March 2004 V. Massaut, The BR3 project – Progress report - Presentation to the TAG 36 meeting, Daejeon, Korea, 10-14 April 2004 V. Massaut - The BR3 project – Progress report Presentation to the TAG 37 meeting,Aachen, Germany, 18-22 October 2004 V. Massaut - Technology issue: an international overview (225/04-01) IAEA Regional Workshop on Decommissioning, Vandellos, Spain, 27/09-01/10/2004 Reports P. Valenduc - Final Report ECDB Net 2 – EC contract FI4D-CT96-0010, Ref. 217/04-15Rev.1 EUNDETRAF - The European Nuclear Decommissioning Training Facility, Final Technical Report – ref. 217/04-07, Contract: FIKR-CT-2001-80123 – FP5 CCE, Reporting period from 01/01/2002 – 31/12/2003 V. Massaut - Identification of decommissioning options for reduction of tritiated waste quantities TWS-TSS-TS W1, Association Euratom-Belgian State, Watching activities in decommissioning R-4007 – Ref. 276/04-13 December 2004 Summary record of the 37th meeting of the Technical Advisory Group, Ref. CPD/PCJ/04/01 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Aachen, Germany, 18-22 October 2004 Training Courses V. Massaut - Application du principe ALARA en démantèlement, Université J. Fourier Grenoble, Valence, 19 January 2004 V. Massaut - BNEN Special Training Course on Decommissioning of Nuclear Installations SCK•CEN, Mol, April 20-21, 2004 Sessions on: - Introduction to Decommissioning: Definitions, objectives, levels, regulatory aspects - Different types of installations from a decommissioning point of view - Strategy and planning of a decommissioning project - Radioprotection, ALARA and Safety - Financial aspects of a decommissioning project M. Ponnet, BNEN Special Training Course on Decommissioning of Nuclear Installations, SCK•CEN, Mol, April 20-21, 2004 Sessions on: - Metal Decontamination Techniques used in Decommissioning Activities - Inventory & Characterization before dismantling J. Dadoumont, BNEN Special Training Course on Decommissioning of Nuclear Installations, SCK•CEN, Mol, April 20-21, 2004, - Dismantling techniques: the BR3 experience E. Cantrel, BNEN Special Training Course on Decommissioning of Nuclear Installations, SCK•CEN, Mol, April 20-21, 2004 - Strategy for the decontamination of buildings, concrete pieces and structures V. Massaut - IBC Summer School on Radioactive Waste Management and Decommissioning Cambridge, 1 July 2004 The Third European Nuclear Decommissioning Training Facility (EUNDETRAF), Third Training Course CEA Saclay, November 22 – December 3, 2004 Sessions on: - Y. Demeulemeester: Material management - V. Massaut: o Financial Aspects of a Decommissioning Project o Metal Decontamination Techniques used in Decommissioning Activities o Decontamination for decommissioning Decontamination of buildings and concrete Contracts E. Cantrel, Chr. Le Goaller - "Strategy for the radiological characterization of the bioshield at the Salaspils research reactor" - End of mission report, 7-11 June 2004, IAEA Technical Co-operation project LAT/4/06-02 Y. Demeulemeester, S. Bodart, V. Massaut - Agreement on the purchase of decommissioning data of the BR3 reactor Phase 3bis, Air data for HPWJC cutting head and bottom, Contract nr. KNT 90 99 1306.03, Ref. 240/04-13, December 2004-January 2005 Conferences & events F. Vermeersch, V. Massaut - Visiplan Users Day, SCK•CEN Brussels, 22 June 2004 Site Restoration Publications N. Impens, M. P. Van Laer, L. Vos, A. J.G. Leenaers, A. F. Fonteyne, S. Dekelver, R. C.P. Vandevoorde, Maltene and soluble salt removal from bituminized waste simulates: fractionation of the waste elements, International journal www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 A. Bruggeman, P. Chaix, J.-P. Glatz, T. Fanghanel, ACTINET: Establishment of a Network of Excellence for Actinide Sciences, Proceedings Euradwaste ’04, Luxembourg, 29.03.2004-31.03.2004 N. Impens, P. Van Bree, J. Van Laer, P. Thomas, L. Vos, A. Fonteyne S. Dekelver, R. Vandevoorde, A. Leenaers, Stability of concentrated bitumen-salt-solvent mixtures, N. Impens et al, STABILITY OF CONCENTRATED BITUMEN-SALT-SOLVENT MIXTURES, proceedings of The 5th International Conference on Petroleum Phase Behaviour and Fouling, 14-17/06 2004 Presentations A. Bruggeman, S. Vanderbiesen, J. Braet, Tritium R&D in SCK-CEN's Chemical Processes Section Tritium meeting at ICSI, Romania, 10 to 12 February 2004 J. Braet, A. Bruggeman, J. Seghers, S. Vanderbiesen, Characterisation of JET waste streams (organic liquids, soft housekeeping waste, contaminated metals) and application of detritiation techniques. JW3-FT-2.15, EFDA/JET, Fusion Technology Task Force Monitoring Meeting, 19 May 2004, Telephone conference J. Braet, A. Bruggeman, S. Vanderbiesen, Testing and demonstration of LPCE for high detritiation factors over a long time, EFDA/JET, Fusion Technology Task Force Monitoring Meeting, 19 May 2004, Telephone conference N. Impens, P. Van Bree, J. Van Laer, P. Thomas, L. Vos, A. Fonteyne, S. Dekelver, R. Vandevoorde, A. Leenaers,Stability of concentrated bitumen-salt-solvent mixtures, The 5th international conference on petroleum phase behaviour and fouling, Banff, Alberta, June 13-17, 2004, Canada A. Bruggeman, P. Goethals, Y-Z Wei, K. Horiguchi, M. Kumagai, Palladium removal from spent nuclear fuel solution using SiPyR-N3 anion exchanger, IEX 2004, 4 - 7 July 2004, Churchill College, University of Cambridge, UK A. Bruggeman, J. Braet, S. Vanderbiesen, Water detritiation: better catalysts for liquid phase catalytic exchange, Tritium 2004 conference, Baden-Baden, Germany, 12-17 September 2004 J. Braet, A. Bruggeman, Oxidation of tritiated organic liquid waste, Tritium 2004 Conference, Baden- Baden, Germany, 12-17 September 2004 J. Braet, A. Bruggeman, S. Vanderbiesen, An overview of SCK•CEN’s technological research for the treatment of tritiated waste, 10 th international Conference "Progress in Cryogenics and Isotopes Separation", Calamanesti, Romania, 13-15 Oktober 2004 N. Impens, Research into possible alternative solutions for the long term management of bituminised radioactive waste, Exchange meeting on bituminised radioactive waste 26/10/2004, SCK•CEN, Mol, Belgium Organised by NIRAS/ONDRAF J. Braet, A. Bruggeman, S. Vanderbiesen, Progress in the testing and demonstration of LPCE for high detritiation factors over a long time, EFDA/JET, Fusion Technology Task Force Monitoring Meeting, 15 November 2004, Telephone conference Reports P. Goethals, D. Penneman, A. Bruggeman, J. Braet, L. Sannen, M. Gysemans, P. Van Bree, G. Verpoucke, DEVELOPMENT OF THE ERIX PROCESS for REPROCESSING SPENT FBR-MOX FUEL – 2003: Pd Recovery Experiment Using a Solution of Irradiated MOX Fuel, Subsequent Electrolytic Reduction Experiment and Chromatographic Separation on AR-01 Anion Exchanger R- 3870 N. Impens, J. Van Laer, R. Vandevoorde, Organic depositions in petroleum industry. Towards the selection of active compounds (II), Contract-report with R-nr-3844 Thesis B. Decelle, De kwantitatieve bepaling en chromatografische scheiding van actiniden, (241Am) en lanthaniden (Nd), Kath. Hogeschool Limburg, Grad. Chemie, 2003-2004 B. Jordens, C. Bortels, Geïntegreerde proef Chemie: Turbimetrie, KTA, Hasselt, April 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 T. Verheyen, Koude simulatie van een gebitumineerd zoutmengsel, KHLIM Diepenbeek, Juni 2004 J. Bertels, Kwantitatieve bepaling van radionucliden via vloeibare scintillatietelling, Groep T thesis, Ind. Ir. Chemie, 2003 – 2004 J. Briat, Fysicochemisch gedrag van bitumen oplossingen, Groep T Leuven, chemie, juni 2004 J. Truyens, Fusie-energie zonder tritiumlozingen: volledige decontaminatie van getritieerde waterstof in een tegenstroomdruipbedreactor, Kath. Hogeschool Limburg, Diepenbeek, juni 2004 J. Camps, Opbouw en testen van de pilootopstelling voor de verwerking van getritieerde organische vloeistoffen, Hogeschool Limburg - Departement industriële Poster International Conference P. Goethals, L. Vos, D. Penneman, A. Bruggeman, Y. Wei, H. Hoshi, M. Kumagai CHROMATOGRAPHIC SEPARATION OF ACTINIDES AND LANTHANIDES FROM FISSION PRODUCTS ON CMPO/SiO2-P EXTRACTION RESIN Sixth International Conference on Nuclear and Radiochemistry (NRC6) 29 August to 3 September 2004 Aachen, Germany Nuclear Chemistry and Services Publications M. Gysemans, M. Van Bocxstaele, P. Van Bree, L. Vandevelde, E. Koonen, L. Sannen, B. Guigon, "Destructive Radiochemical Analysis of Uraniumsilicide Fuel for Burnup Determination", Advances in Nuclear and Radiochemistry, Extended Abstracts, pp. 187-188, 2004. Presentations M. Gysemans, M. Van Bocxstaele, P. Van Bree, L. Vandevelde, E. Koonen, L. Sannen, B. Guigon, "Destructive Radiochemical Analysis of Uraniumsilicide Fuel for Burnup Determination", Sixth International Conference on Nuclear and Radiochemistry (NRC-6), Aachen Germany, 29 August to 3 September 2004. M. Gysemans, Destructive Radiochemical and Chemical Analysis of Nuclear Research and Industrial Materials at NCS, SCK.CEN, Mol September 17, 2004. M. Gysemans, Destructive Radiochemical Analysis of 2 Rebus spent fuel samples, Rebus PWR 4th PCM, Brussels Belgonucléaire, November 19, 2004. M. Gysemans, Destructive Radiochemical Analysis, Topgun/Geronimo Progress Report, Geronimo PCM-4, Topgun PCM-3, Brussels Belgonucléaire, December 9, 2004 Reports M. Gysemans, TOPGUN – Destructive radiochemical analysis for burnup determination – Fuel rod WRCP0950 (G3), SCK.CEN-R-3820, January, 2004. P. Van Bree, Determination of Cu, Ni, Mn, Mo, Cr, Al in ferritic low alloy steels by ICP-MS, Intermediate report,SCK.CEN-R-3931, July, 2004. Training Courses M. Gysemans, Training Radiation Expert SCK.CEN/HL, Module Radiochemistry, 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 BR2 Scientific Output 2004 Publications R. Van Nieuwenhove, L. Vermeeren, "Irradiation effects on temperature sensors for ITER application", Review of Scientific Instruments, 75, 75-83 (2004). Books B. Ponsard, S. Mirzadeh, FF.(Russ)Knapp, "Production of Tungsten-188 in the BR2 Reactor in collaboration with ORNL", paper presented at the 8th IIS International Symposium on the Synthesis and Applications of Isotopes and Isotopically Labelled Compounds, Boston, Massachusetts, USA, June 1-5, 2003. Book edited by John Wiley & Sons, 2004, International Isotope Society, "Synthesis and Applications of Isotopically Labelled Compounds", Volume 8, pp. 103-106, ISBN 0 470 86365 X. Presentations L. Vermeeren, "In-core neutron detection in fission reactors", Workshop on neutron diagnostics at EFDA- JET, Culham Science Centre, 1-2 April 2004. S. Kalcheva, B. Ponsard, E. Koonen, "Reactivity Effects due to Beryllium Poisoning of BR2", paper presented at the PHYSOR 2004 Topical Meeting on The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, Illinois, April 25-29 2004. CD-ROM, American Nuclear Society, LaGrange Park, IL (2004). S. Kalcheva, "Assessment of Fuel Safety Margins with MCNP", Best Estimate Twenty-O-Four (BE-2004), Washington D.C., U.S.A., November 14-18, 2004. Reports P. Jacquet, "Neutron irradiation of titanium alloy specimen", June 2004, R-3927. P. Jacquet, "Neutron irradiation of RAFM samples with implanted helium at 60 and 350°C up to 0.3 dpa for modeling purpose", August 2004, R-3934. P. Jacquet, "Low dose neutron irradiation of titanium alloy samples", August 2004, R-3935. P. Jacquet, "In-situ investigation of the mechanical performance and lifetime of copper in a neutron environment", September 2004, R-4004. S. Kalcheva, "MCNP calculations of Neutron Fluxes for project TANGO", SCK•CEN-R-3827, February 2004. L. Vermeeren, Ph. Gouat, "GERONIMO Ramp Tests at the BR2 Reactor", SCK•CEN-R-3794, January 2004. M. Wéber, “Project OMICO – Gamma heating measurements by means of the mock-up – 2nd campaign (BR2 cycle nr 04/2003)”, SCK•CEN-R-3856, April 2004. M. Wéber, “Project IRINA – Programme description and experimental device design”, SCK•CEN-R-3876, May 2004. M. Wéber, I. Wéber, “FICTIONS-IV - mesure en-pile de la température au centre d’une capsule de carbure de bore: analyse des résultats”, SCK•CEN-R-3958, August 2004. M. Wéber, “Project IRINA – Progress of the experimental device fabrication”, SCK•CEN-R-4052, November 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Conferences V. Kuzminov, E. Koonen, "Irradiation of two UMo fuel plates in BR2", RRFM 2004, Munich 21-24 March 2004. V.Kuzminov, M.Wéber, E.Koonen, "Determination of the Linear Power in MOX Fuel Rods Irradiated at the BR2 Reactor", PHYSOR-2004, Chicago, April 25-29, 2004. L. Vermeeren, “Experimental study of radiation-induced currents in copper and stainless steel core mineral- insulated cables in the BR2 research reactor”, 23rd Symposium on Fusion Technology (SOFT), Venice (Italy), September 20-24, 2004. M. Wéber, R. W. Bosch, L. Vermeeren, "Design and Development of a Multipurpose PWR Rig for In-Core Instrumented Testing ", Int. Conf. Water Chemistry of Nuclear Reactor Systems" San Francisco, USA, October 2004. www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Nuclear Research and Society Scientific Output 2004 Publications Benny Carlé, Perceptie van stralingsrisico's. Mini enquête bij deelnemers van het 40 jaar BVS-ABR colloquium op 24 oktober 2003, Annalen van de Belgische Vereniging voor Stralingsbescherming vol. 28, N° 4, 2003, pp. 375- 388, (2004), ISSN-250-5010 Benny Carlé, Sylvie Charron, Alexandre Milochevitch, Frank Hardeman, An inquiry of the opinions of the French and Belgian populations as regards risk, J. Haz. Mat. Vol. 111 (2004) pp. 21-27 Frank Hardeman, Risk Perception by the Belgian population, Annalen van de Belgische Vereniging voor Stralingsbescherming Vol. 28, N° 4, 2003, pp. 361-373, ISSN-0250-5010 Chloéé Degros, Act on funds for the dismantling of nuclear power plants and the management of irradiated fissile materials in such plants (2003), Nuclear Law Bulletin (OECD,. 72/1, 2004, pp. 72-77 Laes, E., Co-authors: Meskens, G., D'haeseleer, W.,Weiler, R. ‘Trust as a central paradigm for advisory science: the case of the Belgian nuclear phase out’, International Journal of Sustainable Development, vol 7, N°1, pp. 1-26 Isabelle Fucks, Co-author Frank Hardeman, An exploratory Research on Safety Culture According to a Social Science Approach: Lessons related to the 'Promotion' of Safety Culture, 2004 Michel Bovy, Co-authors: Pierre Kockerolls, G. Eggermont, Henri Drymael, Herwig Janssens, Michel Sonck, Mark Van Eijkeren, Hans Vanmarcke, Comment on the 2005 Recommendations of the International Commission on Radiological Protection, Comments of the Belgian Society for Radiation Protection (BVS-ABR), 6 december 2004, published on www.ICRP.org and in the BVS/ABR Newsletter N° 105 van januari-februari-maart 2005 Books Laes, E., Co-authors: Meskens, G.,Ruan, D., ‘Planning for sustainability in the Belgian electricity sector: A multi- criteria mapping exercise’, contribution to ‘Intelligent Sensory Evaluation’ (book ; Springer Verlag, Berlin/Heidelberg/New York, 2004) Laes, E., Chayapathi,L., Meskens, G. en Eggermont, G. (2004), Kernenergie en maatschappelijk debat, rapport in opdracht van het viWTA onderzoeksprogramma 'Energie en Klimaat', Brussel. M. Bovy, Social complexity and the role of the object: installing household waste containers, Chapter in D. Vinck "Everyday engineering, an ethnography of design and innovation", MIT, Massachussets, 2003, pp. 54-75 Presentations Bovy Michel, Eggermont G., Comment favoriser une communication scientifique plus citoyenne ?, national conference, Fondation Roi Baudouin, groupe de travail "les consommateurs ont la parole", groupe "Pionniers" Bruxelles, mai 2004 Gilbert Eggermont, Voorzorg "avant la lettre" of niet in het nucleaire, Gezondheidsraad Nederland, Workshop Voorzorg, Vught, 17 mei 2004 Ludo Veuchelen, Steven Lierman, The optimisation approach of ALARA in nuclear practice: an early application of the Precautionary Principle. Scientific uncertainty, International Symposium on Uncertainty and Precaution in Environmental Management, Copenhagen, 7-9 June, 2004 Chloéé Degros, Marc Beysen Introduction to the compensation of the environments damage arising from a nuclear accident, Séminaire international sur le droit nucléaire et la proctection de l'environnement, 5-9 juillet 2004, Cluj-Napoca, organisé par l'AEN/OCDE G. Eggermont, M. Bovy, Speaking out on environmental threats, rights and responsibiliies "On Lomborg's case – Comment on Edwin Zaccaî position paper, Third University Foundation Ethical Forum, Brussels, 25 november 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 P. Govaerts, Verlies en ongecontroleerd aanwenden van radioactieve bronnen, Koninklijke Academie voor Geneeskunde, Koninklijke Vlaamse Academie voor Wetenschappen en Kunsten en de Belgische Vereniging voor Stralingsbescherming, Ongewenste verspreiding van radioactieve bronnen, Paleis der Academiën, Brussel, 23 oktober 2004 L. Holmstock, Frank Hardeman, Medische interventies binnen het noodplan, Koninklijke Academie voor Geneeskunde, Koninklijke Vlaamse Academie voor Wetenschappen en Kunsten en de Belgische Vereniging voor Stralingsbescherming, Ongewenste verspreiding van radioactieve bronnen, Paleis der Academiën, Brussel, 23 oktober 2004 Reports Hans Vanmarcke, Co-author: G. Eggermont, 2.6. Ioniserende Straling, bijdrage tot het MIRA-T 2004 Milieu en Natuur rapport 2004 Vlaanderen, Vlaamse Milieu Maatschappij, Mechelen (www.vmm.be) Thesis Bombaerts Gunter, Waste Depositionism. A philosophical inquiry on technoscientists and nuclear waste, Doctoraatsverhandeling, UGent, 2004. S. Lierman, Een juridische analyse van het gebruik van ioniserende straling in de klinische geneeskunde: een onderzoek naar de invloed van voorzorg en preventie op gezondheidsbescherming en aansprakelijkheid, doctoraatsverhandeling Universiteit Antwerpen, 2004 Isabelle Fucks, La culture de sûreté selon une démarche compréhensive. Une Contribution à la gouvernance des risques dans des systèmes complexes, Thèse présentée en vue de l'obtention du grade de docteur en sciences politiques , Université de Liège, l octobre 2004 Training Courses Erik Laes, ‘The Belgian decision to phase out nuclear power’, ULg (Liège), ,Workshop 'Théorie de décision et développement durable, March 8, 2004 Bovy Michel, "Stratégie de décisions chez les experts du secteur nucléaire" ULg (Liège), 8 mars 2004 Workshop 'Théorie de décision et développement durable', March 8, 2004 G. Eggermont, Geschiedenis van de stralingsbescherming en de dosimetrie, Opleiding Natuurkundig Ingenieur - Keuzevak Geschiedenis van de Wetenschappen, Museum Wetenschappen, UGent, 22 april 2004 Chloéé Degros, Responsabilité civile spécifique aux accidents nucléaires: un état des lieux, Workshop "Responsabilités environmentales" des centres de droit des obligations des universités UCL et Paris I, Paris, 23- 24 septembre 2004 Bovy Michel, UCL, "Ethics within nuclear decommissioning: what is acceptable for next generations regarding international energy management? UCL, 6 décembre 2004, Analyse des processus de développement en longue période en relation avec la population et l'environnement, Prof. J.P. Van Yperseele Conferences G. Eggermont, M. Bovy, B. Carlé, F. Hardeman, G. Meskens, B. Neerdael, L. Veuchelen, PISA: A transdisciplinary Approach to Integrate Social Sciences in Radiation Protection, Session 9 Societal influences in Radiation Protection – part 9b6, Proc. IRPA-11 International Conference, Madrid 23-28 mei 2004, on CD ISBN 84-87078-05-2, 2004 IRPA-11 or www.irpa11.com (full papers) M. Bovy, Laes E., Why do experts in radiation protection have to cope with public proofs ?, Meeting STS tools for exploring the future, 4 S, European association for the Study of Science and Technology, Paris, 25-28 aug. 2004 Bovy Michel, Laes Erik, How do containers contain society? , international conference, Meeting STS tools for exploring the future, 4 S, European association for the Study of Science and Technology, Paris, 25-28 aug. 2004, G.Eggermont, M. Bovy, Expériences en communication sur la gestion des déchets radioactifs en Belgique, SFEN Conference "Déchets Radioactifs et Communication", Pont-d-u-Gard, Marcoule 15 oktober 2004 G. Eggermont, M. Bovy, B. Feltz and P. Smeesters, Theme 5: Ethical and legal issues, Critical review of ethical and legal issues in the draft 2005 ICRP recommendations, Art 31 Group, RIHSS,EU-Conference, Luxemburg, 4 november 2004 www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 M. Bovy, Laes E., Ethics and funds: an inter-generational equity decided by intra-generational equity, Working party on decommissioning and dismantling radioactive waste management committee OECD/NEA 8-10 nov. 2004, Paris Main contact person: Gilbert Eggermont, [email protected] www.sckcen.be Operational Office: Boeretang 200, B-2400 Mol – Scientific Report 2004 Managing Nuclear Knowledge Scientific output 2004 Publications M.-L. Ruyssen (ed.), 'Topical Day on Knowledge Management in a Scientific Environment'. Book of Abstracts, BA-0001, SCK●CEN, 25 March 25, 2004. Mol, Belgium. Presentations Ch. Legrain, 'Introduction', Topical Day on Knowledge Management in a Scientific Environment. SCK●CEN, March 25, 2004. Mol, Belgium. M. L. Ruyssen, F. Moons, P. Borgermans, 'The Practical Knowledge Management Approach at SCK•CEN', Topical Day on Knowledge Management in a Scientific Environment. SCK●CEN, March 25, 2004. Mol, Belgium. Expert Groups M.L. Ruyssen, 'The SCK•CEN experience on Knowledge Management portals', IAEA Technical Meeting to "Develop a Nuclear Knowledge Portal for the Integration of Existing Nuclear Data and Information Bases", 4-6 October, 2004. Vienna, Austria. M.L. Ruyssen, Chairperson session 'Exploiting Knowledge', EUROSAFE Workshop on Knowledge Management, 14 June 2004, GRS, Köln, Germany. Training Courses M.L. Ruyssen, 'Knowledge Management: van algemene concepten naar een praktische implementatie', Gastcollege Managementstechnieken in de informatiesector, Universiteit Antwerpen, Informatie en Bibliotheekwetenschappen, 7 mei 2004, Wilrijk, België. M.L. Ruyssen, 'Knowledge Management', cursus Post Academische Vorming Industriële Chemie, Universiteit Antwerpen, departement Scheikunde van de faculteit Wetenschappen, Academiejaar 2004-2005. M.L. Ruyssen, 'Knowledge Management', Bijscholingscursus Kennismanagement in organisaties, Bibliotheekschool Vormingsleergang voor Sociaal en Pedagogisch Werk –Gent, najaar 2004. Conferences F. Moons, J. Safieh, M. Giot, B. Mavko, B. R. Sehgal, A. Schäfer, G. van Goethem, W. D'haeseleer, 'European Master of Science in Nuclear Engineering', IAEA–CN–123, IAEA International Conference on Nuclear Knowledge Management: Strategies, Information Management and Human Resource Development. IAEA–CN–123/05/O/1, 7-10 September, 2004. Saclay, France. Poster International Conference F. Moons, W. D'haeseleer, M. Giot, 'BNEN - the Belgian Nuclear higher Education Network: Your Way to the European Master in Nuclear Engineering ', IAEA International Conference on Nuclear Knowledge Management: Strategies, Information Management and Human Resource Development. IAEA–CN–123/05/P/02, 7-10 September, 2004. Saclay, France. M. L. Ruyssen, F. Moons, Ch. Legrain, 'Managing Nuclear Knowledge: a SCK•CEN concern: Status of a Practical Knowledge Management Approach', IAEA International Conference on Nuclear Knowledge Management: Strategies, Information Management and Human Resource Development. IAEA–CN–123/02/P/02, 7-10 September, 2004. Saclay, France. Fusion Scientific Output 2004 Papers B. Brichard, A. F. Fernandez, H. Ooms, F. Berghmans, M. Decréton, A. Tomashuk, S. Klyamkin, M. Zabezhailov, I. Nikolin,V. Bogatyrjov, E. Hodgson, T. Kakuta, T. Shikama, T. Nishitani, A. Costley, G. Vayakis, "Radiation-hardening techniques of dedicated optical fibres used in plasma diagnostic systems", J. Nucl. Mater., 329-333 (2004), pp. 1456-1460. M. Decréton, T. Shikama, E. Hodgson, "Performance of functional materials and Components in a fusion reactor: the issue of radiation effects in ceramics and glass materials for diagnostics", J. Nucl. Mater., 329- 333 (2004), pp. 125-132. F. Druyts, E. Alves, C.H. Wu, "Methods for the mitigation of the chemical reactivity of beryllium in steam", J. Nucl. Mater., 329-333 (2004), pp. 1353-1356. A. Fernandez Fernandez, A. Gusarov, B. Brichard, M. Decréton, F. Berghmans, P. Mégret, A. Delchambre, "Long-term radiation effects on fibre Bragg grating temperature sensors in a low flux nuclear reactor", Measurement Science and Technology, 15 (2004), pp 1506-1511. W. N. Mac Pherson, R. R. J. Maier, J. S. Barton, J. D. C. Jones, A. Fernandez Fernandez, B. Brichard, F. Berghmans, J. C. Knight, P. StJ. Russell, L. Farr, "Dispersion and refractive index measurement for Ge, B- Ge doped and photonic crystal fibre following irradiation at MGy levels", Measurement Science and Technology, 15 (2004), pp 1659-1664. A.-A. F. Tavassoli, A. Alamo, L. Bedel, L. Forest, J.-M. Gentzbittel, J.-W. Rensman, E. Diegele, R. Lindau, M. Schirra, R. Schmitt, H. C. Schneider, C. Petersen, A.-M. Lancha, P. Fernandez, G. Filacchioni, M. F. Maday, K. Mergia, N. Boukos, N. Baluc, P. Spätig, E. Alves, E. Lucon, "Materials design data for reduced activation martensitic steel type EUROFER", J. Nucl. Mater., 329-333 (2004), pp. 257-262. E. Lucon, R. Chaouadi, M. Decréton, "Mechanical Properties of the European Reference RAFM Steel (EUROFER97) Before and After Irradiation at 300 °C", J. Nucl. Mater., 329-333 (2004), pp. 1078-1082. J. Rensman, E. Lucon, J. Boskeljon, J. van Hoepen, R. den Boef, P. ten Pierick, "Irradiation resistance of Eurofer97 at 300 °C up to 10 dpa", J. Nucl. Mater., 329-333 (2004), pp. 1113-1116. C. Domain, C. S. Becquart, L. Malerba, "Simulation of radiation damage in Fe alloys: an object kinetic Monte Carlo approach", J. Nucl. Mater., 335 (2004), pp. 121-145. L. Malerba, D.A. Terentyev, P. Olsson, R. Chakarova, J. Wallenius, “Molecular dynamics simulation of displacement cascades in Fe-Cr alloys”, J. Nucl. Mater., 329-333 (2004), pp. 1156-1160. J. Wallenius, I. A. Abrikosov, R. Chakarova, C. Lagerstedt, L. Malerba, P. Olsson, V. Pontikis, N. Sandberg, D. Terentyev, "Development of an EAM potential for simulation of radiation damage in Fe-Cr alloys", J. Nucl. Mater., 329-333 (2004), pp. 1175-1179. L. Malerba, C.S. Becquart, M. Hou, C. Domain, "Comparison of algorithms for multiscale modelling of radiation damage in Fe-Cu alloys", to appear in Phil. Mag. (2004). D. Terentyev, L. Malerba, "Diffusivity of solute atoms, matrix atoms and interstitial atoms in Fe-Cr alloys: a molecular dynamics study", J. Nucl. Mater., 329-333 (2004), pp. 1161-1165. R. Van Nieuwenhove, L. Vermeeren, "Experimental study of radiation induced electromotive effects on mineral insulated cables", Rev. Sci. Instr., 74 (2004), pp. 4675-4682. L. Vermeeren, R. Van Nieuwenhove, "Theoretical study of radiation induced electromotive effects on mineral insulated cables", Rev. Sci. Instr., 74 (2004), pp. 4667-4674. Presentations B. Brichard, "Radiation induced absorption and luminescence in hydrogen loaded silica fibres", Proceedings of the 13th IEA Workshop on Radiation Effects in Ceramic Insulators”, December 9, 2003, Kyoto (Japan), JAERI-Review-2004-004, March 2004, pp. 10 and 60-61. F. Druyts, D. Mallants, X. Sillen, P. Van Iseghem, "Belgian research on fusion beryllium waste", Proceedings of the 6th International Workshop on Beryllium Technology for Fusion, December 2-5, 2003, Miyazaki (Japan), JAERI-Conf 2004-006, March 2004, pp. 240-248. F. Druyts, E. Alves, C.H. Wu, “Methods for the mitigation of the chemical reactivity of beryllium in steam”, Proceedings of the 6th International Workshop on Beryllium Technology for Fusion, December 2-5, 2003, Miyazaki (Japan), JAERI-Conf 2004-006, March 2004, pp. 103-111. L. Vermeeren, M. Decréton, "Radiation induced electromotive force in cables", Proceedings of the 13th IEA Workshop on Radiation Effects in Ceramic Insulators, December 9, 2003, Kyoto (Japan), JAERI-Review- 2004-004, March 2004, pp. 7 and 35-40. M. Van Uffelen, F. Berghmans, I. Genchev, "Reliability study of photodiodes for their potential use in future fusion reactor environments", Reliability of Optical Components, Devices, Systems, and Networks Conference, Photonics Europe, Strasbourg, April 26-30, 2004, SPIE Proceedings no. 5465, pp. 92-102. B. Brichard, A. Fernandez Fernandez, F. Berghmans, "True dose rate effect on phosporous-doped fibre optic radiation sensor", SPIE Proceedings Int. Soc. Opt. Eng., Second European Workshop on Optical Fibre Sensors, vol. 5502, pp. 184-187, pp. 184-187, June 9-11, 2004, Santander. A. Fernandez Fernandez, G. Rego, A. Gusarov, B. Brichard, J.-L. Santos, H. Salgado, F. Berghmans, "Evaluation of long-period fibre grating temperature sensors in nuclear environments", SPIE Proceedings, Int. Soc. Opt. Eng., Second European Workshop on Optical Fibre Sensors, June 9-11 2004, Santander, vol. 5502, pp 88-91. D.V. Kulikov, L. Malerba and M. Hou, "Vacancy and vacancy-impurity cluster binding energies calculation by a coupled MC and MD quenching technique", 7th Int. Conference on Simulation of Radiation Effects in Solids, Helsinki, June 28 – July 2, 2004. D.A. Terentyev, L. Malerba and M. Hou "In-cascade interstitial cluster formation in concentrated ferritic alloys with strong solute-interstitial interaction: a molecular dynamics study", Proceedings of the 7th International Conference on Computer Simulation of Radiation Effects in Solids, Helsinki, Finland, June 28 – July 2, 2004, to be published in Nucl. Instr. and Meth. B, 2005. M. Matijasevic, A. Almazouzi "Characterisation of Fe-Cr based model alloys" at the NATO International School on Radiation Effects in Solids, Erice, Sicily, Italy, July 17-29, 2004. M. Scibetta, A. Pellettieri, P. Wouters, A. Leenaers, G. Verpoucke, "Design and fabrication of a dead weight equipment to perform creep measurements on highly irradiated beryllium specimens", XXXXII Plenary Meeting of the European Working Group "Hot Laboratories and Remote Handling", Norway, Halden, September 6-8, 2004. A. Bruggeman, J. Braet, "Water detritiation: Better catalysts for liquid phase catalytic exchange", 7th International Conference on Tritium Science and Technology (Tritium 2004), Baden Baden, September 12- 17, 2004, to be published in Fusion Science and Technology, 2005. A. Bruggeman, J. Braet, Sven Vanderbiesen, "Water detritiation: Better SCK•CEN catalysts for liquid phase catalytic exchange", 7th International Conference on Tritium Science and Technology (Tritium 2004), Baden Baden, September 12-17, 2004, to be published in Fusion Science and Technology, 2005. J. Braet, A. Bruggeman, "Oxidation of tritiated organic liquid waste", 7th International Conference on Tritium Science and Technology (Tritium 2004), Baden Baden, September 12-17, 2004, to be published in Fusion Science and Technology, 2005. Gh. Ionita, A. Bornea, J. Braet, I. Popescu, I. Stefanescu, N. Bidica, C. Varlam, C. Postolache, L. Matei, "Endurance test for SCK•CEN catalytic mixed packing, proposed for water detritiation system at JET", 7th International Conference on Tritium Science and Technology (Tritium 2004), Baden Baden, September 12- 17, 2004, to be published in Fusion Science and Technology, 2005. S. Rosanvallon, N. Bekris, J. Braet, P. Coad, G. Counsell, I. Cristescu, C. Grisolia, F. Le Guern, J. Likonen, A. Perevezentsev, G. Piazza, C. Poletiko, M. Rubel, J.M. Weulersee, J. Williams, "Tritium related studies within JET fusion technology work programme", 7th International Conference on Tritium Science and Technology (Tritium 2004), Baden Baden, September 12-17, 2004, to be published in Fusion Science and Technology, 2005. E. Lucon, R.-W. Bosch, L. Malerba, S. Van Dyck and M. Decréton, "An Integrated Approach to Fusion Material Research At SCK•CEN", 16th ANS Topical Meeting on the Technology of Fusion Energy (TOFE), Madison, Wisconsin (USA), September 14-16, 2004, to be published in Fusion Science and Technology, 2005. E.J. Alves, L.C. Alves, A. Paúl, N. Franco, A. Sequeira, H. Hegeman, F. Druyts, "Characterization and stability studies of titanium beryllides", presented at the 23rd Symposium on Fusion Technology, September 20-24, 2004, Venice, Italy, to be published in Fusion Engineering and Design, 2005. F. Druyts, "Corrosion of fusion-specific waste materials", Presented at the 23rd Symposium on Fusion Technology, September 20-24, 2004, Venice, Italy, to be published in Fusion Engineering and Design, 2005. A. F. Fernandez, A. Gusarov, B. Brichard, F. Berghmans, M. Decréton, "Fibre optic sensors networks for environmental and safety monitoring of fusion reactors", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004. S. Girard, B. Brichard, J. Baggio, J-L. Bourgade, M. Decréton, F. Berghmans, "Vulnerability of optical fibres for plasma diagnostics of Laser MegaJoule", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. A. Giraud, M. Van Uffelen, F. Berghmans, "Use of electronic and optoelectronic industrial systems for maintenance tools of ITER Fusion experimental reactor", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. A. Gusarov, L. Vermeeren, B. Brichard, A. Fernandez, H. Ooms, M. Decréton, F. Berghmans, "In-situ in- reactor testing of fusion materials and components", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. R. Lindau, A. Möslang, M. Reith, M. Klimiankou, E. Morris, A. Alamo, F. Tavassoli, C. Cayron, A. Lancha, P. Fernandez, N. Baluc, R. Schaüblin, E. Diegele, J. Rensman, B. van der Schaaf, E. Lucon, W. Dietz, "Present development status of Eurofer and ODS for application in blanket concepts", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. P. Moilanen, S. Tähtinen, P. Jacquet, J. Dekeyser, B. Singh, "Development of experimental devices for in- reactor mechanical tests", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. A. Neri, B. Brichard, L. Bartolini, A. Coletti, M. Ferri de Collibus, G. Fornetti, F. Pollastrone, M. Riva, L. Semeraro, "Experimental result of the laser In-Vessel Viewing and ranging System (IVVS) for ITER", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. J. Palmer, S. Mikko, P. Agostini, R. Gottfried, M. Irving, A. Tesini, M. Van Uffelen, "Recent developments towards ITER divertor maintenance", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. S. Tähtinen, B. Singh, P. Moilanen, P. Jacquet, J. Dekeyser, D. Edwards, "Deformation behaviour of copper under in-reactor uniaxial tensile tests", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. S. Van Dyck, R.-W. Bosch, "Environmental assisted cracking of Eurofer 97 in water and Pb-Li", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, September 20-24, 2004, to be published in Fusion Engineering and Design, 2005. L. Vermeeren, "Experimental study of radiation-induced currents in copper and stainless steel core mineral- insulated cables in the BR2 research reactor", presented at the 23rd Symposium on Fusion Technology (SOFT), Venice, Italy, 20-24 September 2004, to be published in Fusion Engineering and Design, 2005. A. Gusarov, H. Ooms "SCK·CEN in-situ radiation tests: prototype bolometers with Pt meander on alternative substrates and Radiation-Induced Electric Degradation (RIED)", Satellite Meeting on Radiation Effects in Ceramics, 23rd Symposium on Fusion Technology, Venice, Italy, September 22, 2004. M. Van Uffelen, A. Giraud, F. Berghmans, "High gamma dose assessment of a multimode analogue fibre optic transmitter", RADECS-2004 Workshop, Madrid, September 22-24, 2004. S. O’Keeffe, C. Fitzpatrick, A. Fernandez Fernandez, B. Brichard, F. Berghmans, E. Lewis, "Evaluation of PMMA optical fibres as gamma dosimeters for nuclear applications", Proceedings of the Plastic Optical Fibres Conference (POF-2004), Nuremberg, September 27-28, 2004. M. Van Uffelen, I. Genchev, F. Berghmans, "Radiation effects on Si and InGaAs p-i-n photodiodes", ESA Workshop op Optical Wireless On-board Communications, ESTEC, Noordwijk, September 29-30, 2004. B. Brichard, "Improvement of radiation-resistance of silica optical fibres for plasma diagnostic system by glass hydrogen-treatment", ITPA Diagnostics Group Technical Meeting, October 11-14, 2004, Hefei, China. B. Brichard, "Radiation resistance of optical fibre sensors for ITER: Thermography, RTDS and Fibre Optic Current", ITPA Diagnostics Group Technical Meeting, October 11-14, 2004, Hefei, China. D.A. Terentyev, L. Malerba, Yu.N. Osetsky and A.V. Barashev, "Single interstitial cluster diffusion in bcc Fe- Cr alloys: a molecular dynamics study", Proceedings of the 2nd Intl. Conf. on Multiscale Modelling of Materials, Los Angeles, USA, October 11-15, 2004. J. Braet, A. Bruggeman, S. Vanderbiesen (invited), "An overview of SCK•CEN’s technological research for the treatment of tritiated waste", 10th International Conference Progress in Cryogenics and Isotopes Separation (ICSI), Calamanesti (Romania), October 13-15, 2004. G. Ionita, A. Bornea, J. Braet, I. Popescu, I. Stefanescu, N. Bidica, C. Varlam, C. Postolache, L. Matei, "Endurance test for SCK•CEN catalytic-mixed packing, proposed for water detritiation system at JET", 10th International Conference Progress in Cryogenics and Isotopes Separation (ICSI), Calamanesti (Romania), October 13-15, 2004. Reports D. Sapundjiev, R.W. Bosch, "Liquid Metal Embrittlement (LME) of Fusion Materials in Pb-17Li, Part I Literature review and design hot cell SSRT set-up", SCK•CEN Report, R-3819, January 2004. J. Braet, A. Bruggeman, "Endurance test for the catalyst-packing mixture proposed for Water Detritiation system at JET, using SCK•CEN mixture", Final Report of Task JW4-FT-2.20, D1, SCK•CEN Technical Note, TN-17, February 2004. F. Druyts, "Corrosion of fusion-specific waste material in a clay geological repository", Final report on task UT-BER-2003, SCK•CEN Report, R-3848, March 2004. Ph. Benoit, "High temperature irradiation devices", Final report task TW2-TTMS-001-D15, SCK•CEN Report, R-3850, March 2004. M. Scibetta, A. Pellettieri and P. Wouters, "Design and fabrication of a dead weight equipment to perform creep measurements on highly irradiated beryllium", SCK•CEN Report, BLG-979, April 2004. M. Scibetta, A. Pellettieri and P. Wouters, "Qualification of a dead weight equipment to perform creep measurements on highly irradiated beryllium", SCK•CEN Report, BLG-980, April 2004. D.V. Kulikov, L. Malerba and M. Hou, "On the binding energies of copper-vacancy complexes in iron-copper alloys: a computational study", SCK•CEN Report, BLG-956, May 2004. A. Leenaers, S. Van den Berghe and L. Sannen, "Sample preparation of highly irradiated beryllium", SCK•CEN Report, R-3862, June 2004. P. Jacquet, "Neutron Irradiation of Titanium alloy specimens", Final Report Task TW1-TVM-TITAN-D3, SCK•CEN Report, R-3927, June 2004. A. Fernandez Fernandez, "Assessment of Fibres for Fusion Applications", Final Report of task UT-OF-2003, SCK•CEN Report, R-3932, June 2004. P. Jacquet, "Neutron Irradiation of RAFM samples with implanted helium at 60 and 350°C up to 0.3 dpa for modelling purpose", Final Report task TW2-TTMS-001-D17, SCK•CEN Report, R-3934, August 2004. P. Jacquet, "Low dose neutron irradiation of Titanium alloy samples", Final Report task TW3-TVM-TICRFA- D2, SCK•CEN Report, R-3935, August 2004. M. Matijasevic, K. Verheyen, W. Van Renterghem, A. Almazouzi, "Introduction to TEM observation of ferritic material: Theory and practice", SCK•CEN Report, BLG 993, September 2004. B. Brichard, "Optical performance of a hydrogen-loaded optical fibre during the 2003 Deuterium-Tritium traces at JET", SCK•CEN Report, R-3933, September 2004. J. Braet, A. Bruggeman, S. Vanderbiesen, J. Seghers, "Characterisation of JET waste streams (organic liquids, soft housekeeping waste, contaminated metals) and application of detritiation techniques", Final Report of Task JW3-FT-2.15, SCK•CEN Report, R-3939, September 2004. P. Jacquet, "In-situ investigation of the mechanical performance and lifetime of copper in a neutron environment", Final Report Task TW2-TVV-SITU, SCK•CEN Report, R-4004, September 2004. D. Maisonnier et al., "A conceptual study of commercial fusion power plants", Final report of the European power plant conceptual study (PPCS), EFDA-RP-RE-5.0 Report, September 2004 (with SCK•CEN contribution from F. Druyts, D. Mallants, V. Massaut, M. Klein and L. Ooms). B. Brichard, "Radiation effects on large diameter optical fibres", Final report of tasks TW3-TPD/IRRCER-D10 and TW4-TPD/IRRCER-D4, Part I, SCK•CEN Report, R-3960, October 2004. S. Van Dyck, R-W. Bosch, "Compatibility of Eurofer97 Reduced Activation Ferritic Martensitic steel with hydrogen and liquids – Stress Corrosion Cracking of neutron irradiated Eurofer97 in high temperature water”, Final report of task TW2-TTMS-003a-D11 and Part I of TW2-TTMS-003b-D3, SCK•CEN Report, R-4020, October 2004. F. Druyts, "Be12Ti interaction with air and steam at HCPB BB relevant temperatures: Interim report on the results in air", SCK•CEN report, R-4038, October 2004. F. Druyts, "Chemical reactivity of dust and flakes and D mobilisation experiments from co-deposited layers", Final report of task TW0-T438, SCK•CEN Report, R-4039, October 2004. D. Mallants, "Acceptability of beryllium waste in near surface waste disposal sites", Final report of Task TW1- TSW-002-D6, SCK•CEN Report, R-4043, November 2004. V. Massaut, “Watching activities in decommissioning”, Final report of Task TW3-TSS-TSW1-D1, SCK•CEN Report, R-4007 (in preparation), November 2004. B. Brichard, "Radiation effects on large diameter optical fibres", Final report of tasks TW3-TPD/IRRCER-D10 and TW4-TPD/IRRCER-D3, Part II, SCK•CEN Report, R-4008, December 2004. R. Chaouadi, "Flow and fracture properties of 9%Cr ferritic/martensitic steels", report in preparation, December 2004. R. Chaouadi, "High temperature deformation and crack resistance behaviour of 9%Cr ferritic/martensitic steels", report in preparation, December 2004. M. Matijasevic, A. Almazouzi "Characterisation of as received Fe-Cr based alloys", report to be issued in December 2004. BSc Theses K. Bemelmans, "Development of a measurement set-up for the characterization of wavelength tunable laser diodes" (in Dutch), undergraduate work, Katholieke Hogeschool Kempen, Geel, Belgium, June 2004. J. Camps, "Construction and test of a pilot installation for the treatment of tritiated organic liquids" (in Dutch), Bachelor thesis, Hogeschool Limburg, 2004. Y. Descas, "Photobleaching of Irradiated Optical Fibre", Master thesis, University Montpellier II, 20. S. Harnist, "Development and characterisation of OSL detectors (Optically Stimulated Luminescence)" (in French), Master thesis, University Montpellier II, 2004. B. Melis, "Characterisation of RADFET dosimeters at high gamma radiation doses" (in Dutch), Graduate thesis, Katholieke Hogeschool Kempen, 2004. P. Rodeghiero, "Feasability study of an optical Raman Distributed Temperature Sensor (RDTS) in a nuclear environment", Master thesis, Univ. Liège, 2004. J. Truyens, "Fusion energy without tritium release: total decontamination of tritiated liquids in a counter current trickle bed reactor" (in Dutch), Bachelor thesis, Hogeschool Limburg, 2004.