BE0100012
HAMD AIT ABDERRAHIM
MYRRHA PROJECT: A MULTIPURPOSE ACCELERATOR DRIVEN SYSTEM (ADS) FOR R&D
Scientific Staff Background field of reactor materials, fuel and reactor physics HAMID AIT ABDERRAHIM, research; Nuclear energy has to cope with critical topics to THIERRY AOUST, enhancement and triggering of new R&D activi- resolve the economical question of increasing energy BAUDOUIN ARIEN, ties such as nuclear waste transmutation, ADS demand and, in particular, the public acceptability PETER BAETEN, technology, liquid metal embrittlement; LEON BAETSLE, demands: initiation of medical applications such as proton JEAN-LUC BELLEFONTAINE, S increasing the absolute safety of the installations; therapy and PET production, or proton based irra- PHILIPPE BENOIT, 5 managing more efficiently the nuclear waste. diation programmes. GILBERT BERGMANS, SERGE BODART, In that respect, the development of a new type of The present MYRRHA concept, as described below, RACHID CHAOUADI, nuclear installation coping with above constraints of is determined by the versatility of the applications it SIMON COENEN, technological as well as socio-economical nature would allow. Further technical and/or strategic CHARLES DE RAEDT, may be of high importance for the future of sustain- developments of the project might change the pres- PIERRE D'HONDT, able energy provision. An Accelerator Driven ent concept. PETER KUPSCHUS, System or ADS, - a subcritical core, operated as a The design of MYRRHA needs to satisfy a number ENRICO LUCON, waste burner for minor actinides (MAs) and long of specifications such as: EDOUARD MALAMBU, lived fission products (LLFPs) or as nuclear amplifi-
NADIA MESSAOUDI, er for energy production, fed with primary neutrons m achievement of the neutron flux levels required
JAN PEETERS, by a spallation source - has the potential to cope with by the different applications considered in
PEDRO RODRIGUES DE above constraints and to pave the way to a more MYRRHA;
ALMEIDA, environmentally safe and acceptable nuclear energy 15 2 D 4>>0.75Mev = 1.0 x 10 n/cm .s at the locations for VlTALI SOBOLEV, production. Fundamental and applied R&D are cru- minor actinide (MA) transmutation;
SVEN VAN DEN BERGHE, cial in the development of these technologies and 13 14 2 E ®>t MeV = 1.0 x 10 to 1.0 x 10 n/cm .s at the STEVEN VAN DYCK, demand the availability of appropriate prototype locations for structural material and fuel irradia- KLAAS VAN DER MEER, installations. These prototype installations have to tion; RUDI VAN NIEUWENHOVE, investigate and have to deal with the R&D-issues O = -2.0 x 1015 n/cm2.s at locations for long- KATRIEN VAN TICHELEN, related to accelerator driven system development. th lived fission product (LLFP) transmutation or FERNAND VERMEERSCH, radioisotope production; MARK VERWERFT, The continuation of nuclear science and engineering
HARM WIENKE, demands the availability of research installations, i.e. sub-critical core total power: ranging between 20
YVES JONGEN (IBA), research reactors, and these are currently subject to and 30 MW;
DIRK VANDEPLASSCHE (IBA). constraints related to ageing, high operational costs, criticality level: keff < 0.95 in all conditions, as in deep refurbishment or even replacement. A new, a fuel storage, to guarantee inherent safety; Supporting staff inherently safe, and economically viable system is called for that could be used in a modular way for a operation of the fuel under safe conditions: lead- STEFAN DEKELVER, dedicated applications, to extend known research ing to an average fuel pin linear power not JOHAN MERCKEN, domains and to explore new ones. exceeding 500 W/cm. TONY VAN NIEUWENHUYSEN Currently the study and preliminary conceptual design of the MYRRHA system is going on. We Programme started the basic engineering. The main effort in In accordance with this philosophy, SCK'CEN and 2000, was dedicated to improve the pre-design of the IBA s.a., Ion Beam Applications, are developing spallation source and the sub-critical core for jointly the MYRRHA project, a multipurpose neu- answering the high irradiation performance require- tron source for R&D applications on the basis of an ments of MYRRHA and to assess the most risky Accelerator Driven System (ADS). This project is points of the pre-design. intended to fit into the European strategy towards an ADS Demo facility for nuclear waste transmutation Achievements but should also serve as an irradiation facility for the particular needs of SCK'CEN. In its present status of development, the MYRRHA project is based on the coupling of an upgraded com- We can group the R&D applications that are consid- mercial proton cyclotron with a liquid Pb-Bi win- ered in the future MYRRHA facility in three blocs: dowless spallation target, surrounded by a sub-criti- :; continuation, and extension, towards ADS of the cal neutron multiplying medium in a pool type con- ongoing R&D programmes at SCK'CEN in the figuration as shown in the figure below. The spalla-
86 Reactor Safety tion target circuit is fully separated from the core The Accelerator coolant as a result of the windowless design present- IBA is conducting preliminary design studies on the ly favoured in order to utilise low energy protons accelerator required for MYRRHA. The present without reducing drastically the core performances. design of the sub-critical core requires the accelera- The core pool contains a fast spectrum core, cooled tor to deliver a 350 MeV, 5 mA proton beam. This with liquid Pb-Bi and several islands housing ther- 1.75 MW continuous wave beam has to satisfy a mal spectrum regions located in In-Pile Sections at number of requirements, some of which are unique the periphery of the fast core. The fast core is fuelled in the world of accelerators up to now. At this level with typical fast reactor fuel pins with an active of power it is compulsory to obtain an extraction effi- length of 600 mm arranged in hexagonal assemblies ciency above 99.9% and a very high stability of the of 122 mm plate-to-plate. The central hexagon posi- beam, but on top of that the ADS application needs a tion is left free for housing the spallation module. reliability well above that of common accelerators, The present core is made of 18 fuel assemblies of bringing down the beam trip frequency (trips longer which 12 have a Pu content of 30% and 6 a Pu con- than a few tenths of a second) to below 1 per day. tent of 20% but alternatives are still being evaluated. The design principles are based on the following lines of thought: The MYRRHA design is determined by the require- ment of versatility in applications and the desire to Si Statistics show that the majority of beam trips are use as much as possible existing technologies. The due to electric discharges (both from static and heat exchangers and the primary pump unit are to be radiofrequency electric fields). Hence the highest embedded in the reactor pool. The accelerator is to be reliability requires minimising the number of installed in a confinement building separated from electrostatic devices, which favours a single stage the one housing the sub-critical core and the spalla- design. tion module. The proton beam will be impinging on In order to obtain the very high extraction effi- the spallation target from the top. ciency, two extraction principles are available: through a septum with well-separated turns, or by stripping. The beams are dominated by space charge. Binding Magnet Therefore one needs careful transverse and longi- tudinal matching at injection, and avoiding of Thermal neutron Island cross talk between adjacent turns (by an enhanced turn separation) if a separated turn structure is Proton Beam Line required for the extraction mechanism.
The space charge dominated proton beam needs a 20-mm turn separation at 350 MeV if a septum extraction has to be implemented. This solution requires the combination of a large low-field magnet and of very high RF acceleration voltages for realis- Spallation Target Loop ing such a large turn separation, and also an electro- Fast Core static extraction device. In view of what precedes, this solution is not well suited for very high reliabil- ity operation. Extraction by stripping does not need separated turns. It may be obtained by the accelera- tion of H- ions, but the poor stability of these ions makes them extremely sensitive to electromagnetic Global view of the present design of MYRRHA stripping (and hence beam loss) during acceleration. The use of H" would, therefore, lead to the use of an In the following paragraphs we give the achieve- impracticably large magnetic structure. The other ments reached in 2000 for the various components of solution is to accelerate 2.5 mA of HH+ ions up to the facility. 700 MeV, where stripping transforms them into 2 protons of 350 MeV each, thus dividing the magnet- ic rigidity by 2 and thereby allowing extracting. This solution reduces the problems related to space charge
Reactor Safety 87 since only half the beam current is accelerated. results for the neutron multiplicity. They agreed with However, the high magnetic rigidity of a 700 MeV the predicted values by means of the HETC code HH+ beam imposes a magnetic structure with a pole within 10%. The full set of expected data from this radius of almost 7 m, leading to a total diameter of programme are: the cyclotron of close to 20 m. The cyclotron would a neutron multiplicity or amount of spallation neu- consist of 4 individual magnetic sectors, each of trons per incident proton (n/p yield); them spanning 45 degrees. a spallation neutron energy spectrum; At the present stage of R&D the last option appears 53 spallation neutron angular distribution; to be the most appropriate one. a spallation products created in the Pb-Bi target.
The Spallation Source Feasibility of the windowless design The following considerations dictated the choice of a windowless design: The design of the windowless target is very chal- lenging: a stable and controllable free surface needs as at about 350 MeV, an incident proton delivers 7 to be formed within the small space available in the MeV kinetic energy per spallation neutron. fast core centre (0 120 mm). We will bombard Almost 85% of the incident energy exit the target outer this free surface with protons, giving rise to a large in the form of "evaporation" energy of the nuclei. and concentrated heat deposition (1.75 MW) dis- The addition of a window would diminish the persed over a 12 cm depth starting from the surface fraction of the incident energy delivered to the for a proton energy of 350 MeV. This heat needs to spallation neutrons; be removed to avoid overheating and possible evap- ffl a windowless design avoids vulnerable parts in oration of the liquid metal. the concept, increasing its reliability and avoiding a very difficult engineering task; To gain confidence and expertise in the possibility of creating a stable free surface, SCK'CEN conducted B because of the very high proton current density an R&D program in collaboration with the thermal- (> 130 uA/cm2) and the limitation of the available hydraulics department of the Universite Catholique diameter of the central hole housing the spallation de Louvain-la-Neuve (UCL, Belgium). Within this module and the low energy proton beam we R&D program, water experiments on a one-to-one intend to use, a window in the MYRRHA spalla- scale were performed. Water was used because of its tion module would undergo severe embrittlement. good fluid-dynamic similarity with Pb-Bi. This pro- The project team has identified three main risks to be gramme was complemented by velocity field meas- assessed for this windowless design: urements in collaboration with Forschungszentrum Rossendorf (FZR, Germany) using ultrasonic veloc- ity profile and hot-wire techniques. Currently, the Need for basic spallation data design of the spallation target is fine-tuned and adapted to the latest geometrical constraints imposed Since the flux characteristics in an ADS are deter- by the neutronics of the fast core. In 2000, we devel- mined by the spallation neutron intensity and since oped a design intended to answer the geometrical as there is a lack of experimental spallation data in the well as the hydraulics constraints to be able to proton energy range considered for MYRRHA, remove the total heat deposition. Due to air entrap- SCK'CEN is assessing the basic spallation data ment on the top of the free surface when trying to when bombarding a thick Pb-Bi target with protons reduce the stagnant zone at the free surface, we came at energies ranging between E = 350 to 590 MeV. A p to the limitation of the water development pro- joint team from SCK'CEN, PSI (Paul Scherrer gramme. Institute, Switzerland) and NRC-Soreq (Nuclear Research Centre, Israel) conducts the experimental A confirmation experimental programme making use programme at the PSI proton irradiation facility of Hg as a fluid started in 2000 at the Institute of (PIF). The programme started in December 1998 and Physics at the University of Latvia (IPUL) at Riga. finished by the end of October 2000 for the experi- At SCK'CEN we fabricated a 1:1 scale spallation mental part. The analysis of the data is still going for module nozzle (see figure below). We tested it at the some results mainly the spallation product analysis end of the year 2000. The first test showed that a and the energy spectrum. We obtained preliminary modification against the water simulations with
88 Reactor Safety increased inlet to outlet speed ratio to accommodate ments. We will use the CFD (Computer Fluid severe spatial design constraints leads to a non-toler- Dynamics) calculations to investigate the flow pat- able turbulence in the recycling zone with droplet tern and temperature profile in the presence of the formation from the free surface. We carried out a proton beam, which cannot be simulated experimen- modified nozzle re-design which brought this ratio tally at this stage. At SCK-CEN the CFD modelling back to about 1 and this will now be tested in a sub- is performed with the FLOW-3D code which is spe- sequent campaign early 2001. cialised for free surface and low Prandtl number flow. This effort is being backed up at the Universite Catholique de Louvain-la-Neuve (UCL, Belgium) using the FLUENT code. Moreover, we set up a col- laboration agreement with Nuclear Research Group - Petten (NRG, The Netherlands) for more CFD calcu- lations with the STAR-CD code.
Compatibility of the windowless; free surface with the proton beam line vacuum
As the free surface of the liquid metal spallation source will be in contact with the vacuum of the pro- ton beam line, SCK«CEN is concerned about the quantitative assessment of emanations from the liq- uid metal. These can lead to the release of volatile spallation products, Pb and Bi vapcurs and of Po, which will be formed by activation of Bi. These radioactive and heavy metal vapours can contami- nate the proton beam line and finally the accelerator, making the maintenance of the machine very diffi- cult or at least very demanding in terms of manpow- er exposure. The MYRRHA spallation module scale 1:1 for Hg tests at the University of Latvia. In order to assess the feasibility of the coupling between the liquid metal of the target and the vacu- As a final confirmation, we will run experiments in um of the beam line and to assess the types and quan- 2001 with the real fluid at the actual MYRRHA oper- tities of emanations, SCK«CEN is preparing the ation conditions (temperatures, vacuum and fluid VICE experiment (Vacuum-Interface Compatibility velocity) in collaboration with: Experiment), studying the coupling of a vacuum a FZK (Karlsruhe, Germany) where the MYRRHA stainless steel vessel containing 130 kg Pb-Bi, heat- spallation target head will be inserted in the ed to temperatures up to 500°C, with a vacuum tube KALLA large hydraulic Pb-Bi-loop, which has a (104 ~ 10'6 mbar) simulating the proton beam line. A working temperature range of 250 - 450 °C. mass spectrometer will measure the initial and final These tests will address the full spallation target out-gassing of light gasses and the: metal vapour circuit aspects; migration. To protect the vessel from liquid metal B ENEA (Brasimone, Italia) where the MYRRHA corrosion, we currently investigate the possibility of injection nozzle spallation target will be tested in using Mo and W coatings. the CHEOPE Pb-Bi loop without a complication of a full technical loop. The vessel is fabricated at SDMS (France) and is undergoing commissioning tests at 500°C. The mass In parallel with the experiments, we perform numer- spectrometer has been delivered by HIDEN (UK) ical simulations using Computational Fluid and will be commissioned and tested, early 2001. Dynamics codes aimed both at reproducing the exist- The site for the VICE experiment is ready and ing experimental results and at giving input for the accepted by the internal safety authority of optimisation of the head geometry in the experi- SCK'CEN.
Reactor Safety 89 The Sub-critical core content) and the second one of 12 fuel assemblies of which 6 are 30% enriched and 6 are 20% enriched. The design of the sub-critical assembly will have to As an alternative we consider to go to smaller fuel yield the neutronic performances and provide the assemblies to limit the radial burn-up and swelling irradiation volumes required for the considered gradients within the fuel assembly, and in order to applications. To meet the goals of material studies, possibly achieve better fuel management. fuel behaviour studies, radioisotope production, transmutation of MAs and LLFPs, the subcritical We carried out neutronic calculations coupling the core of MYRRHA must include two spectral zones: high energy transport code HETC and the lower a fast neutron spectrum zone and a thermal spectrum energy neutron transport deterministic code DORT one. and the Monte Carlo code MCNP-4B for simulating typical configurations of the fast core. This led to encouraging results showing that the targeted per- Fast zone description formances could be achieved. The table illustrates the results we obtained for a particular configuration. In the currently assumed design, we will place the fast core centrally into a liquid Pb-Bi pool, leaving the central hexagonal assembly empty for housing the spallation target. The core consists of hexagonal Thermal zone description assemblies of MOX FR-type fuel pins with a Pu-con- We changed completely the initial design, with a tent, Pu/(Pu+U), ranging from 20% to 30%, arranged water pool surrounding the fast core zone and hous- in a triangular lattice with a pitch of 10 mm. The fuel ing the thermal neutron core zone, for evident safety pins have an active fuel length of 60 cm and their reasons (water penetration into the fast core). In the cladding consists of 9% Cr martensitic steel. The fuel present approach the thermal zone will be kept at the pins are arranged in typical FR fuel hexagonal fast core periphery, but it will consist of various In- assemblies with an assembly dimension of 122 mm Pile Sections (IPS) to be inserted in the Pb-Bi liquid plate-to-plate in the present design. The fast zone is metal pool from the top of the reactor cover. Each made of 2 concentric crowns, the first one consisting IPS will contain a solid matrix made of moderating of 6 highly enriched fuel assemblies (with 30% Pu material (ZrH2, Be, C, "B4C) on which a total leak- age flux of 1 to 3 1015 n/cm2.s will impinge. Local boosters made of fissile materials can be considered depending on the particular performance needed in Neutronic Parameters Unit Value the thermal neutron IPS. Black absorbers settled around the IPS could ensure the neutronic de-cou- MeV 350 pling of the thermal islands from the fast core. First
IP mA 5 MCNP-4B results of thermal islands surrounded with ZrH2 indicated non perturbed thermal fluxes n/p-yield 4,40 ranging between 1 to 2 1015 n/cm2.s. Intensity (£„ < 20 MeV) 1O17 n/s 1,23
Keff 0,948 Engineering and Safety Studies for 1K, 0,959 MYRRHA IF 1,29 MF = 1 / ( 1 - K.) 24,51 We continued configurational studies using the Thermal Power MW 32.2 Pro/ENGINEER and AUTOCAD CAD systems dur- Avg Power density W/cm3 232 ing the year 2000 to develop mechanical design spec- Peak linear Power W/cm 475 ifications and to study the remote handling require- ments of fuel loading and handling machines and *>i M«V 10" n/cm*s § systems maintenance for the heat exchangers and the XI around the target 0,83 primary pumps. These studies have led to a maxi- first fuel ring 0,73 mum core diameter of lm and a pool vessel maxi- 15 z I
90 Reactor Safety prior to core loading as well as of used assemblies for For the sub-critical reactor building, tliree options are the minimum cool-down before removal from the being assessed: pool. A robot arrangement for the exchange and ffl re-using an existing confinement building where transfer of the fuel has been conceived and thoughts the operators are not allowed to enter during the have been given to the visibility problem under liq- operation of the system; uid metal. Also submerged in the pool will be the pri- mary pumps and heat exchangers; the latter will use ffi re-using an existing confinement building where water .as the secondary coolant and the safety impli- the operators are allowed to enter during the oper- cations of this possible choice are still under review. ation of the system, which means that the dose The interior design of the pool will permit the emer- exposure is less than 10 uSv/h. A preliminary gency cooling for the LOF case (loss of flow) by free assessment showed that lateral shielding of 1 m convection. In a first round the fuel handling and steel followed by 2 m heavy concrete would be component exchange activities outside the pool have necessary for achieving such a radiation level due been analysed with respect to the control of poloni- to the very high neutron leakage. These prelimi- um a-emitter contamination and according design nary estimates are based on analytical estimates measures are now in progress. One of the larger as well as on MCNP modelling; problems lies in the required final biological shield- si designing a completely new building with the 2 ing to attenuate the fast neutrons (with energies close access options considered above. to the one of the protons) and an optimising exercise is going on here to minimise costs. Perspectives A vertical view of the present design is given below. In 2001, we intend to finalise the pre-design phase and to provide a cost assessment of the project to pre- pare a decision by the management on the next stage of the development of the project, namely the detailed engineering design phase.
CEA Commissariat a l'F.iwrgie Atomique (Cadarache and Saclay, France).
ENEA Ente Per Le Nuove Tecnologie, l'Energia E l'Ambiente (Brasimone and Bologna, Italy)
FZK ForschungsZentrum Karlsruhe (Karlsruhe, Germany) FZR ForschungsZentrum Rossendorf (Rossendorf, Germany)
IBA Ion Beam Applications (Louvain- la-Neuve, Belgium)
IPUL Institute of Physics of University of Latvia (Riga, Latvia) Vertical cut of the MYRRHA Engineered sub-critical core and spallation loop. NRC Nuclear Research Centre (Soreq, Israel) Parallel to the core and the spallation module design, NRG Nuclear Research Group (Petten, attention is given therefore to the confinement build- The Netherlands) ing where the MYRRHA subcritical reactor includ- ing the spallation module will be located.' The accel- PSI Paul Scherrer Institute (Villigen, erator will be kept in a separate confinement building Switzerland) to facilitate the maintenance and inspection proce- UCL University Catholique de Louvain dures. (Louvain-la-Neuve, Belgium)
Reactor Safety 91 CFD Challenges for a Windowless Spallation Target Design", presented at Topical Day on ADS, Mol, October Publications 24* 2000. H. Ait Abderrahim, P. Kupschus, E. Malambu, Ph. Benoit, H. Ait Abderrahim, "MYRRHA, An ADS for R&D in sup- K. Van Tichelen, B. Alien, F. Vermeersch, P. D'hondt, Y. port for the European ADS Programme", presented at Jongen, S. Ternier, D. Vandeplassche, "MYRRHA: A Topical Day on ADS, Mol, October 24th 2000. Multipurpose Accelerator Driven System for Research & H. Wienke, "Processing of New Cross-Section Libraries Development", Nuclear Instruments and Methods in with NJOY for ADS Applications", presented at Topical Physics Research (NIMA 13054), 2000. Day on ADS, Mol, October 24th 2000. M. Coeck, Th. Aoust, F. Vermeersch, H. Ait Abderrahim, Presentations "Shielding Assessment of the MYRRHA Accelerator Driven System using the MCNP Code", Proceedings H. Ait Abderrahim, P. Kupschus, E. Malambu, Ph. Benoit, Monte Carlo 2000, Lisbon, Portugal, October 23-26 2000. K. Van Tichelen, B. Aden, F. Vermeersch, P. D'hondt, Y. Jongen, S. Temier, D. Vandeplassche, "MYRRHA: A H. Ait Abderrahim, "Ongoing Activities in Belgium in the Multipurpose Accelerator Driven System for Research and field of ADS and P&T", proceedings IAEA Technical Development", presented at the International Youth Committee Meeting on "Core Physics and Engineering Nuclear Congress 2000, Bratislava, Slovakije, April 9-14 Aspects of Emerging Nuclear Energy Systems for Energy 2000. Generation and Transmutation", Argonne National Laboratory, Argonne, USA, November 28- December 1, H. Ait Abderrahim, P. Kupschus, E. Malambu, K. Van 2000. Tichelen, Ph. Benoit, B. Alien, F. Vermeersch, S. Bodart, Th. Aoust, Ch. De Raedt, "MYRRHA, a small ADS K. Van Tichelen, P. Kupschus, H. Ait Abderrahim, J-M Actinide-Transmuter Prototype. Current Status of the Seynhaeve, G. Winckelmans, H. Jeanmart, F. Roelofs, E. Project", Sixth CAPRA/CADRA Seminar, Newby Bridge, Komen, "MYRRHA: Design of a Windowless Spallation Cumbria, England, June 26-28, 2000. Target for a Prototype Accelerator Driven System", pro- ceedings IAEA Technical Committee Meeting on "Core H. Ait Abderrahim, P. Kupschus, E. Malambu, Ph. Benoit, Physics and Engineering Aspects of Emerging Nuclear K. Van Tichelen, B. Arien, F. Vermeersch, P. D'hondt, Y. Energy Systems for Energy Generation and Jongen, S. Ternier, D. Vandeplassche, "MYRRHA: A Transmutation", Argonne National Laboratory, Argonne, Multipurpose Accelerator Driven System for Research & USA, November 28-December 1, 2000. Development", presentation GEDEON Workshop, Cadarache - France, September 20-21, 2000. H. Ait Abderrahim, P. Kupschus, E. Malambu, Ph. Benoit, K. Van Tichelen, B. Arien, F. Vermeersch, P. D'hondt, Y. K. Van Tichelen, P. Kupschus, H. Ait Abderrahim, J-M. Jongen, S. Ternier, D. Vandeplassche, "MYRRHA: A Seynhaeve, G. Winckelmans, H. Jeanmart, F. Roelofs en E. Multipurpose Accelerator Driven System for Research & Komen, "MYRRHA: Design of a Windowless Spallation Development", proceedings IAEA Technical Committee Target for a Prototype Accelerator Driven System", 10* Meeting on "Core Physics and Engineering Aspects of International Conference on Emerging Nuclear Energy Emerging Nuclear Energy Systems for Energy Generation Systems (ICENES 2000), Petten, September 24-28, 2000. and Transmutation", Argonne National Laboratory, H. Ait Abderrahim, P. Kupschus, E. Malambu, Ph. Benoit, Argonne, USA, November 28-December 1, 2000. K. Van Tichelen, B. Arien, F. Vermeersch, Y. Jongen, S. H. Ait Abderrahim, P. Kupschus, E. Malambu, Ph. Benoit, Temier, D. Vandeplassche, "MYRRHA: A Multipurpose K. Van Tichelen, B. Arien, F. Vermeersch, P. D'hondt, Y. Accelerator Driven System for Research & Development", Jongen, S. Ternier, D. Vandeplassche, "MYRRHA: A paper presented at the 10* International Conference on Multipurpose Accelerator Driven System for R&D as first Emerging Nuclear Energy Systems (ICENES 2000), step towards Waste Transmutation. Current Status of the Petten, September 24-28, 2000. th Project", proceedings 6 OECD/NEA Information H. Ai't Abderrahim, P. Kupschus, E. Malambu, Ph. Benoit, Exchange on Actinide and Fission Product Partitioning and K. Van Tichelen, B. Arien, F. Vermeersch, P. D'hondt, Y. Transmutation, Madrid, Spain, December 11-13, 2000. Jongen, S. Ternier, D. Vandeplassche, "MYRRHA: A Ph. Benoit, H. Alt Abderrahim, P. Kupschus, E. Malambu, Multipurpose Accelerator Driven System for Research & K. Van Tichelen, B. Arien, F. Vermeersch, P. D'hondt, Y. Development", Symposium "Energie et Developpement Jongen, S. Ternier, D. Vandeplassche, "MYRRHA: A Durable", ISIB-Brussel, October 11-12, 2000. Multipurpose Accelerator Driven System for Research & K. Van Tichelen, P. Kupschus, H. Ait Abderrahim, Development", Advisory Group Meeting on "Design & "Thermal-Hydraulic Challenges for Heavy Liquid Metals: Performance of Reactor and Subcritical Blanket Systems
92 Reactor Safety and Lead/Bismuth as Coolant and/or Target Material", V. Sobolev, S. Van Dyck, "Compatibility of Liquid Lead Moscow, Russian Federation, October 23 - 27, 2000. and Liquid Lead-Bismuth Eutectic with Structure Materials (Brief Review)", internal report VS/SVD/rw 32.B043006-85/MYRRHA-00-80, December 2000. Reports E. Malambu, "Neutronic Performance Assessment of the MYRRHA ADS Facility", SCK'CEN R-Report-3438-B, March 20, 2000. V. Sobolev, Ph. Benoit, P. Kupschus, H. Ait Abderrahim, "Some Estimates about Applicability of a Gas Coolant in the MYRRHA Sub-Critical Core", internal report VS/PhB/PK/HAA.vs 32.B043006-85/MYRRHA- Concept/00-64, August 2000. Ph. Benoit, "Calculation Note: Preliminary Design of the MYRRHA Heat Exchangers", internal report PhB/phb.32.B043006 85/MYRRHA-Design/00-62, August 22, 2000. K. Van Tichelen, "Neutronic Analysis of some incidental situations in the MYRRHA Sub-Critical Core", BLG- Rapport 850, eindwerk voorgedragen tot het bekomen van de graad van Gediplomeerde in de Gespecialiseerde Studies Nucleaire Techniek, K.U.Leuven, Faculteit Toegepaste Wetenschappen, September 2000. E. Malambu, "Progress Report on Neutronic Assessment of the MYRRHA ADS Facility" SCK-CEN R-Report 3474, October 26, 2000. G. Van den Eynde, "A Review of Accelerator Driven System Dynamics Literature", internal report GVdE/gvde- 34.D047000-85/00-18a, November 2000. Th. Aoust, "Neutronic Assessment of the MYRRHA ADS Using the Monte Carlo Code MCNP4B", technical note RF&M, Tha/tha-34/B043001/85/00-12, 2000. V. Sobolev, "Pressure Drop, Pitch and Fuel Fraction in an Inner Cell of the MYRRHA Fuel Bundle", internal report VS/vs 32.B043006-85/MYRRHA-Design/00-73, October 2000. V. Sobolev, "An Attempt to Optimise HEX Design and Thermal Regime", internal report VS/vs 32.B043006- 85/MYRRHA-Design/00-76, October 2000. V. Sobolev, P. Van Uffelen, "Benchmark Test of the codes FRAPCON-3 and FEMAXI-V with FUMEX reference data", technical note VS/PVU/vs 32 B043006/D055420- 85/MYRRHA/THOMOX/00-78, October 2000. V. Sobolev, "Optimisation of the MYRRHA Reference Fuel Rod Assembly: Temperature Increment and Flow Rate", internal report VS/vs 32.B043006-85/MYRRHA- Design/00-116, November 2000. V. Sobolev, "Reference Fuel Assembly ofMYRRHAADS: concept and pressure drop", internal report VS/vs 32.B043006-85/MYRRHA-Design/01-08, December 2000.
Reactor Safety 93