INSTITUTE OF ATOMIC ENERGY
ANNUAL REPORT 2007
______Otwock-Świerk, Poland
Editorial Committee:
Jacek J. Milczarek Mieczysław Zielczyński Andrzej Strupczewski Jan K. Maurin Ewa Szlichcińska
Editor: Grażyna Swiboda
IAE Otwock-Świerk, 2007 Pr.1337, 13.12.2006 r.
FOREWORD
The Institute’s of Atomic Energy main topic is safe energy generation with particular emphasis on nuclear energy as the most environment friendly technology. This has been expanded into the realm of hazards analysis and its applications to conventional plants. After Polish Government decision of 2005 on the use of nuclear power for electricity generation, the Institute in cooperation with few universities started training of students in the nuclear safety and radiation protection. The Institute takes part in preparation of expertise reports as well as research and education programs crucial for the implementation of nuclear power plants in Poland. The ionizing radiation protection issues furnish the basis of our health physics research. Material science studies performed mainly with non-destructive nuclear techniques like neutron scattering and Mössbauer spectroscopy or X-rays form an important part of our research.
The Institute of Atomic Energy operates the multifunctional nuclear research reactor MARIA. In 2007 the reactor was successfully operated for 4002 hours with a new type of fuel elements of 36% enrichment in U-235. No radiological accidents, failures or breakdowns due to the fuel behavior were recorded in 2007, confirming the good quality of the new fuel. The new fuel elements’ integrity monitoring system was performing its task efficiently. The main technological applications of the MARIA reactor are: radioactive isotopes production, neutron doping of silicon and minerals properties modification. The Reactor Facility for Neutron Transmutation Doping of Silicon Single Crystals was used in doping of single crystalline and multicrystalline silicon wafers.
One of our main goals is to provide the scientific community of Poland an easy access to the source of neutrons. This involves widest possible applications of MARIA reactor in research and technology. The beams of thermal neutrons are used in neutron scattering and radiography studies of condensed matter structures and processes occurring at various levels of length scales.
66 papers describing the results of our research were published in 2007. Some of the results were accounted for in 141 IAE Reports as the preliminary step before publication. Several new results obtained in 2007 on water migration in granular media, properties of ion
beams modified materials as well as extensive use of synchrotron topography in crystal defects studies should be mentioned. The recombination methods for assessment of mixed radiation doses at various facilities were mastered.
The studies on models and software tools for emergency management were carried out within the EU Framework projects by the Centre of Excellence Management of Health and Environmental Hazards MANHAZ.
The Materials Testing Centre formed within a consortium of the IAE and the Radioactive Waste Management Plant for quick identification and categorization of unidentified or of unknown origin radioactive or nuclear items acts as an important link to the Polish response system to illicit trafficking and inadvertent movement of radioactive materials.
Our institute is open for the community. We are proud that above 5000 visitors came to enjoy our presentations and lectures on nuclear techniques developed on the basis of nuclear research reactor MARIA during 2007. Several students from Polish and foreign universities obtained student summer training in IAE laboratories in 2007.
The fusion of the Institute of Atomic Energy and the Centre of Isotope Production POLATOM, appears to be very advantageous and resulted in the substantial increase in the number of projects, publications and other accomplishments in 2007.
Krzysztof Wieteska
CONTENTS
GENERAL INFORMATION ...... 1
OPERATION AND SAFETY OF MARIA REACTOR
G. Krzysztoszek, A. Gołąb, J. Jaroszewicz OPERATION OF THE MARIA RESEARCH REACTOR...... 15
K. Andrzejewski, T. Kulikowska, Z. Marcinkowska UPGRADE OF MARIA REACTOR MODEL FOR OPERATIONAL PREDICTIONS IN 2007 ...... 20
RADIATION PROTECTION AND DOSIMETRY
B. Filipiak, N. Golnik, Z. Haratym, E. T. Józefowicz, K. Józefowicz, T. Pliszczyński, B. Snopek THE ACTIVITIES OF THE RADIATION PROTECTION MEASUREMENTS LABORATORY...... 23
M. Zielczyński, N. Golnik, M.A. Gryziński DETERMINATION OF INITIAL RECOMBINATION OF IONS CREATED IN QUASI-PULSED RADIATION FIELDS ...... 26
N. Golnik, M. Zielczyński NEUTRON-TO-GAMMA SENSITIVITY RATIO OF THE RECOMBINATION CHAMBER AS A FUNCTION OF NEUTRON ENERGY ...... 27
J. Ośko, N. Golnik MONTE CARLO CALCULATION OF NaI DETECTOR FOR IODINE 131I IN THYROID ...... 28
M.A. Gryziński RELATIVE NEUTRON SENSITIVITY OF IONIZATION CHAMBER FILLED WITH HYDROCARBON GASES ...... 29
M. Zielczyński, N. Golnik RELATIVE LOCAL IONIZATION DENSITY – CORRELATIONS WITH MICRODOSIMETRIC PARAMETERS...... 30
K. Józefowicz, B. Boimski, P. Tulik, M. Zielczyński RADIATION FIELDS OF GAMMA IRRADIATOR IN CALIBRATION ROOM OF RADIATION PROTECTION MEASUREMENTS LABORATORY ...... 31
I NUCLEAR TECHNOLOGY IN ENERGY GENERATION
S. Kilim, E. Strugalska-Gola, M. Szuta, A. Wojciechowski, Z.Woźnicki, G. De Cargouet STAND AT THE MARIA RESEARCH REACTOR FOR THE STUDIES OF TRANSMUTATION OF FISSION PRODUCTS AND INCINERATION OF MINOR ACTINIDES...... 35
M. Bielewicz, S. Kilim, E. Strugalska-Gola, M. Szuta, A. Wojciechowski RESULTS OF Y-89 IRRADIATION ON U/Pb-ASSEMBLY USING 1.6 GeV DEUTERON BEAM FROM THE JINR NUCLOTRON...... 36
M. Szuta UO2 GRAIN SUBDIVISION FOR VERY DEEP BURN-UP AND RELATIVELY LOW TEMPERATURE AND ITS IMPACT ON FISSION GAS RELEASE ...... 37
A. Wojciechowski, M. Szuta ADVANCES IN THE SUB-CRITICAL MC CALCULATIONS FOR THE YALINA THERMAL FACILITY...... 38
M. Klisińska PRESENT STATUS OF IV-GENERATION LEAD-COOLED FAST REACTORS DEVELOPMENT...... 39
S. Chwaszczewski, J. Szczurek, P. Czerski, M. Łuszcz NUCLEAR POWER COMPONENT IN FORESIGHT ON ENERGY IN POLAND...... 40
B. Słowiński, R. Sobczak CORRELATION BETWEEN MULTIPLICITY, RAPIDITY AND IMPACT PARAMETER IN PION-XENON INTERACTIONS AT GeV ENERGIES...... 41
B. Słowiński, P. Duda, W. Dzikowski PARAMETRIZATION OF FLUCTUATION OF ENERGY LOSS IN ELECTROMAGNETIC CASCADES AT INTERMEDIATE ENERGIES ...... 42
B. Słowiński, P. Duda, M. Sikorski SEARCH FOR THE UNIVERSAL PARAMETERIZATION OF ELECTROMAGNETIC PROFILES IN HEAVY AMORPHOUS MEDIA...... 43
A. Strupczewski ANALYSIS OF PROSPECTS OF WIND ENERGY IN POLAND ...... 44
A. Strupczewski, K. Jaworska, A. Patrycy, G. Saniewski FACTORS IMPLYING THE IMPLEMENTATION OF NUCLEAR POWER IN POLAND...... 45
II
CONDENSED MATTER PHYSICS
J. J. Milczarek, J. Jankowska-Kisielińska, A. Czachor REGIONAL LABORATORY OF NEUTRONOGRAPHY...... 49
A. Czachor, J. J. Milczarek NEUTRON AND GAMMA RADIOGRAPHY STATION AT THE NUCLEAR RESEARCH REACTOR MARIA ...... 50
W. Szteke MATERIAL RESEARCH LABORATORY OF THE IEA...... 52
A. Czachor, P. Pęczkowski NUCLEAR POTENTIAL WELLS AND BOUND ENERGY STATES AS EVALUATED FROM EXPERIMENTAL DATA ON NEUTRON SCATTERING LENGTHS...... 53
K. Wieteska, W. Wierzchowski , A. Malinowska, M. Lefeld-Sosnowska, W. Graeff GROWTH DEFECTS AND LATTICE DEFORMATION IN Ca0.5Sr0.5NdAlO4 SINGLE CRYSTAL...... 54
K. Wieteska, W. Wierzchowski, J. Gronkowski, G. Kowalski, T. Słupiński, W. Graeff SYNCHROTRON TOPOGRAPHIC INVESTIGATION OF BULK GaAs1–xPx AND GaAs1–x Px:Te CRYSTALS ...... 55
K. Kołodziejak, W. Wierzchowski, K. Wieteska, M. Malinowski, W. Graeff, T. Łukasiewicz CRYSTALLOGRAPHIC DEFECTS AND FACETING IN Er-DOPED Yb3Al5O12 CRYSTALS...... 56
K. Wieteska, W. Wierzchowski, E. Wierzbicka, A. Malinowska, M. Lefeld-Sosnowska, T. Łukasiewicz, W. Graeff TOPOGRAPHIC STUDIES OF GROWTH DEFECTS IN YVO4 CRYSTALS ...... 57
K. Wieteska, W. Wierzchowski, C. Pochrybniak, J. J. Milczarek, W. Graeff SYNCHROTRON DIFFRACTION STUDIES OF MONO- AND MULTICRYSTALLINE SILICON DOPED BY NEUTRON TRANSMUTATION IN MARIA REACTOR...... 58
J. Jankowska-Kisielińska, I. Fijał-Kirejczyk, K. Mikke ANISOTROPY OF THE NEUTRON SCATTERING ON THE Mn0.71Ni0.29 ALLOY ...... 59
J.J. Milczarek, I. Fijał-Kirejczyk, J. śołądek , M. Chojnowski, G. Kowalczyk, Z. Jurkowski, J. śołądek EFFECT OF GRAVITATION ON WATER MIGRATION IN GRANULAR MEDIA...... 60
J.J. Milczarek, I. Fijał-Kirejczyk, J. śołądek, J. Banaszak, Z. Jurkowski, J. śołądek NEUTRON RADIOGRAPHY STUDIES OF DRYING KAOLIN SAMPLES...... 61
J.J. Milczarek, E. Iller, J. śołądek, I. Fijał-Kirejczyk, Z. Jurkowski, J. śołądek NEUTRON SCATTERING STUDIES OF WO3:ZrO2 NANOCOMPOSITES ...... 62
A. Stoch, P. Guzdek, P. Stoch, J. Pszczoła, J. Suwalski, P. Zachariasz, T. Wójcik
MÖSSBAUER EFFECT STUDIES OF Dy(Fe0.7-xNixCo0.6)2 ...... 63
A. Stoch, P. Guzdek, P. Stoch, J. Pszczoła, J. Suwalski, P. Zachariasz, T. Wójcik
BAND STRUCTURE CALCULATION OF Dy(Fe0.7-X NiXCo0.6)2 INTERMETALLICS ...... 64
P. Stoch, J. Suwalski, P. Zachariasz, T. Wójcik STRUCTURE AND PROPERTIES OF 137Cs CONTAINING WASTE GLASS ...... 65
III J. K. Maurin, A. Krukowski, Z. Czarnocki N-(2-AMINOPHENYL)-1-[(1S,2R)-2-HYDROXY-7,7-DIMETHYLBICYCLO[2.2.1]HEPT-1- YL]METHANESULFONAMIDE, A NEW LIGAND FOR ASYMMETRIC TRANSFER HYDROGENATION...... 66
J. Balzarini, B. Orzeszko, J. K. Maurin, A. Orzeszko SYNTHESIS AND ANTI-HIV STUDIES OF 2-ADAMANTYL-SUBSTITUTED THIAZOLIDIN-4-ONES ...... 67
B. Paluchowska ENERGY DECOMPOSITION ANALYSIS AND ECTRON DENSITY CHARACTERIZATION OF HETEROCYCLIC DIMERS INTERMOLECULAR INTERACTIONS...... 68
B. Paluchowska INTERMOLECULAR INTERACTIONS OF HETERORING OXYGEN AND SULPHUR BY FINGERPRINTS OF HIRSHFELD SURFACE...... 69
L. Górski, A. Pawłowski DIFFRACTION DATA AND MICROSTRUCTURE OF Al2O3 – SiO2 COATINGS ...... 70
R. Wiśniewski, B. Słowiński, A.Yu. Didyk, T. Wilczyńska EVIDENCE FOR IMPLANTATION INDUCED CHANGE OF THERMO-RESISTANE PROPERTIES OF MANGANIN UNDER HIGH PRESSURE...... 71
T. Wilczyńska, R. Wiśniewski, V. Semina, A. Didyk PROPERTY OF MANGANIN AFTER HIGH DOSE Ti AND Kr IMPLANTATION...... 72
R. Wiśniewski, T. Wilczyńska HIGH PRESSURE EFFECTS IN CASTOR AND RAPE OIL...... 73
M. Turek, K. Pyszniak, A. Droździel, D. Mączka, J. Sielanko MODELLING OF BEAM EXTRACTION FROM HOLLOW CATHODE ION SOURCES ...... 74
K. Pyszniak, M. Turek, A. Droździel, D. Mączka, J. Sielanko SPUTTERING OF Ti TARGET WITH MEDIUM ENERGY Ar+ BEAM...... 75
NUCLEAR TECHNIQUES IN HEALTH AND ENVIRONMENT PROTECTION MANAGEMENT OF HAZARDS
CENTRE OF EXCELLENCE MANHAZ – MANAGEMENT OF HEALTH AND ENVIRONMENTAL HAZARDS...... 79
M. Borysiewicz SYSTEM SECURITY RISK ANALYSIS ...... 80
M. Borysiewicz, S. Potempski , W. Kacprzyk POLLUTANT AIR CONCENTRATION PREDICTION SYSTEM FOR URBAN AGGLOMERATIONS ...... 81
M. Borysiewicz, L. Czerski, J. Dyczewski, I. Garanty, A. Kozubal, S. Potempski, A. Wasiuk, H. Jędrzejec, H. Wojciechowicz THE SIMULATIONS OF EMERGENCY SITUATIONS CAUSED BY ACTS OF TERROR WITH THE USAGE OF TOXIC OR RADIOACTIVE SUBSTANCES IN URBAN AREAS...... 82
M. Borysiewicz SPATIAL PLANNING OF PREVENTING AND ABATEMENT MEASURES IN THE CONTEXT OF MAJOR ACCIDENTS...... 83
IV M. Borysiewicz, I. Garanty, A. Kozubal DIRECT COSTS OF NUCLEAR TREATIES, AGREEMENTS AND AGENCIES ...... 84
M. Borysiewicz, Ł. Czerski, J. Dyczewski, I. Garanty, A. Kozubal, S. Potempski, A.Wasiuk, H. Wojciechowicz THE CALCULATION MODELS FOR ASSESSMENT OF TERRORIST THREATS IN AQUEOUS ENVIRONMENT AND URBAN POTABLE WATER DISTRIBUTION NETWORK ...... 85
S. Potempski THE APPLICATION OF MM5 NUMERICAL WEATHER PREDICTION SYSTEM FOR HIGH RESOLUTION SIMULATIONS ...... 86
S. Potempski, S. Galmarini APPLICATION OF THE ENSEMBLE SYSTEM TO ANALYSIS OF ETEX EXPERIMENT...... 87
S. Potempski, S.Galmarini IMPROVING OFF-SITE EMERGENCY MANAGEMENT: DEMONSTRATION PROJECTS UNDER EURANOS FRAMEWORK...... 88
M. Borysiewicz SECURITY OF INDUSTRIAL CONTROL SYSTEMS...... 89
M. Borysiewicz, J. Dyczewski, M. A. Borysiewicz USE OF HPAC PACKAGE FOR RISK SIMULATION IN RELEASE OF DANGEROUS SUBSTANCES IN THE ATMOSPHERE...... 90
M. Borysiewicz, Ł. Czerski, H. Wojciechowicz PRESENTATION OF FLUENT PACKAGE CAPABILITIES ...... 90
A. G. Chmielewski, A. Ostapczuk, J. Licki THE EXPERIMENTAL STUDY OF VOCs REMOVAL FROM EXHAUST GASES USING THE ELECTRON BEAM FROM AN ACCELERATOR...... 91
RADIOISOTOPE CENTRE POLATOM
K. Małetka, A. Markiewicz, R. Mikołajczak, E. Byszewska-Szpocińska, T. Dziel RADIOISOTOPE CENTRE POLATOM...... 95
I. Cieszykowska, M. Mielcarski ELECTROCHEMICAL PROCESSES OF FIXING RADIONUCLIDES APPLIED IN SEALED SOURCES FOR BRACHYTHERAPY...... 96
J. Pijarowska, A. Jaroń, E. Iller THE DEVELOPMENT OF A PREPARATION METHOD OF ALBUMIN MICROSPHERES AS POTENTIAL RADIONUCLIDE CARRIERS FOR DIAGNOSTIC AND THERAPEUTIC USE...... 97
E. Byszewska-Szpocińska, U. Karczmarczyk, J. Michalik, M. Górska-Chrząstek, J. Kapuściński, J. Kuśmierek NEW DIAGNOSTIC KIT HYNIC-IGG LABELLED WITH TECHNETIUM-99m FOR INFLAMMATION IMAGING...... 98
R. Mikołajczak, D. Pawlak, M. Zuchlińska, M. Konior, J.L. Parus THE DEVELOPMENT OF A 188W/188Re GENERATOR FOR THE THERAPEUTIC USE ...... 99
R. Broda, T. Dziel, A. Muklanowicz, A. Listkowska, Ł. Pieńkowski, A. Patocka, E. Kołakowska THE INTERCOMPARISON OF 99mTc AND 131I MEASUREMENTS BY RADIONUCLIDES CALIBRATORS IN POLISH HOSPITALS 2007...... 100
V R. Broda ON PHOTON STATISTICS IN THE LS-COUNTER...... 101
E. Iller, H. Polkowska-Motrenko, D. Wawszczak, M. Konior SYNTHESIS AND TESTING OF GEL METAL-OXIDE COMPOSITES AS FILLING MATERIALS FOR W-188/Re-188 GENERATOR COLUMNS...... 102
T. Dziel, R. Broda DEVELOPMENT OF RADIONUCLIDES STANDARDIZATION METHODS BY MEANS OF A LIQUID SCINTILLATORS TECHNIQUE USING MONTE CARLO CALCULATIONS...... 103
PUBLICATIONS, SEMINARS, CONFERENCES...... 107
Author Index...... 143
VI
ORGANIZATION SCHEME
NUCLEAR SCIENTIFIC SAFETY DIRECTOR COUNCIL COMMISSION
DEPUTY DIRECTOR SCIENTIFIC SECRETARY DEPUTY DIRECTOR FOR NUCLEAR SAFETY DEPUTY DIRECTOR CENTRE OF EXCELENCE FOR REACTORS AND RADIOLOGICAL MANHAZ PROTECTION
DEPUTY DIRECTOR Department Department FOR ADMINISTRATION of Nuclear Methods MATERIAL RESEARCH of Maria Reactor AND MAINTENANCE in Solid State Physics LABORATORY
Department Department of Reactor Analysis CHIEF ACCOUNTANT of Nuclear Energy and Technology RADIATION PROTECTION MEASUREMENTS LABORATORY
Cyfronet Computing Center
RADIOISOTOPE CENTRE POLATOM
Information Center ANNUAL REPORT 2007 General Information
MANAGING STAFF
Director Krzysztof Wieteska, Ph.D., D.Sc. Phone 022 718 00 01
Scientific Secretary, Stefan Chwaszczewski, Ph.D., D.Sc. Phone 022 718 00 04 Deputy Director
Deputy Director, Administration Henryk Michałowski, M.Sc. Phone 022 718 00 03 and Maintenance
Chief Accountant Walentyna Kruszewska Phone 022 718 00 02
Deputy Director for Reactors Grzegorz Krzysztoszek, M.Sc. Phone 022 718 00 80
Deputy Director for Nuclear Safety and Phone 022 718 03 33 Jerzy Kozieł, M.Sc. Radiation Protection
RESEARCH DEPARTMENTS AND LABORATORIES
B2 Department of Nuclear Methods Prof. A. Czachor, Ph.D., D.Sc. Phone 022 718 01 18 in the Solid State Physics
Phone 022 718 00 30 B3 Department of Nuclear Energy Prof. S. Chwaszczewski, Ph.D., D.Sc. 022 718 03 04
Phone 022 718 00 61 LBM Material Research Laboratory W. Szteke, M.Sc.
NC Centre of Excellence MANHAZ M. Borysiewicz, Ph.D. Phone 022 718 01 32
NS Radiation Protection Measurement Z. Haratym, Ph.D. Phone 022 718 02 00 Laboratory 022 718 00 32
Regional Laboratory J. J. Milczarek, Ph.D. Phone 022 718 02 33 SLN of Neutronography
Phone 022 718 00 18 BC Computing Center CYFRONET A. Szarek
OINTEA Scientific, Technical and Economic E. Szlichcińska, M.Sc. Phone 022 718 00 07 Information Centre POLATOM Radioisotope Centre K. Małetka Ph.D. Phone 022 718 07 00
5 General Information ANNUAL REPORT 2007
SCIENTIFIC COUNCIL (2003 - 2007)
The Scientific Council was elected on 3 June 2003 by the scientific, technical and administrative staff of the Institute. The Council has the right to confer Ph. D. degree in physics.
Krzysztof Andrzejewski, Ph.D. Institute of Atomic Energy
Waldemar Biłous, Ph.D. Institute of Atomic Energy
Mieczysław Borysiewicz, Ph.D. Institute of Atomic Energy
Prof. Mieczysław Budzyński, Ph.D., D.Sc. Maria Curie Skłodowska University, Lublin
Prof. Andrzej Chmielewski, Ph.D., D.Sc. Institute of Nuclear Chemistry and Technology
Prof. Stefan Chwaszczewski, Ph.D., D.Sc. Institute of Atomic Energy
Prof. Ludwik Dąbrowski, Ph.D., D.Sc. Institute of Atomic Energy
Prof. Roman Wacław Domański, Ph.D., D.Sc. Institute of Heat Engineering, Warsaw University of Technology
Andrzej Furtek, M.Sc. Institute of Atomic Energy
Natalia Golnik, Ph.D., D.Sc. Institute of Atomic Energy, Warsaw University of Technology
Zbigniew Haratym, Ph.D. Institute of Atomic Energy
Rajmund Janczak, Ph.D. Institute of Heat Engineering, Warsaw University of Technology
Joanna Jankowska-Kisielińska, Ph.D. Institute of Atomic Energy
Janusz Jaroszewicz, M.Sc. Institute of Atomic Energy
Paweł Jarzembowski, M.Sc. Institute of Atomic Energy
Edward T. Józefowicz, Ph.D., D.Sc. Institute of Atomic Energy
Grzegorz Krzysztoszek, M.Sc. Institute of Atomic Energy
Prof. Tadeusz Kulik, Ph.D., D.Sc. Warsaw University of Technology
Teresa Kulikowska, Ph.D. Institute of Atomic Energy
Prof. Stanisław Kuliński, Ph.D., D.Sc. Soltan Institute for Nuclear Studies
Janusz Licki, Ph.D. Institute of Atomic Energy
Jan K. Maurin, Ph.D. Institute of Atomic Energy
Henryk Michałowski, M.Sc. Institute of Atomic Energy
Prof. Janusz R. Mika, Ph.D., D.Sc. Warsaw Management Academy
Jacek J. Milczarek, Ph.D. Institute of Atomic Energy
6 ANNUAL REPORT 2007 General Information
Tomasz Pliszczyński, M.Sc. Institute of Atomic Energy
Prof. Jan Pluta, Ph.D., D.Sc, Faculty of Physics, Warsaw University of Technology
Zdzisław Rusinowski, Ph.D. Institute of Atomic Energy
ElŜbieta Strugalska-Gola, Ph.D. Institute of Atomic Energy
Marcin Szuta, Ph.D., D.Sc. Institute of Atomic Energy
Prof. Jan Suwalski, Ph.D., D.Sc. Institute of Atomic Energy
Ewa Szlichcińska, M.Sc. Institute of Atomic Energy
Lech Marian Waliś, Ph.D. Institute of Nuclear Chemistry and Technology
Jan Wasiak, Ph.D. Institute of Atomic Energy
Prof. Tadeusz Wasiutyński, Ph.D., D.Sc. Institute of Nuclear Physics, Krakow
Krzysztof Wieteska, Ph.D., D.Sc. Institute of Atomic Energy
Henryk Wojciechowicz, M.Sc. Institute of Atomic Energy
Tadeusz Wójcik, Ph.D. National Atomic Energy Agency
Zbigniew I. Woźnicki, Ph.D., D.Sc. Institute of Atomic Energy
Prof. Mieczysław Zielczyński, Ph.D., D.Sc. Institute of Atomic Energy
Chairman of the Scientific Council: Prof. Janusz R. Mika, Ph.D., D.Sc. Deputy chairmen: Natalia Golnik, Ph.D., D.Sc., Prof. Stanisław Kuliński, Ph.D., D.Sc. Secretary: Edmund Kmiotek, Ph.D . . Deputy secretary: Teresa Kulikowska, Ph.D.
7 General Information ANNUAL REPORT 2007
SCIENTIFIC COUNCIL (2007 –2008)
The Scientific Council was elected on 5 June 2007 by the scientific, technical and administrative staff of the Institute. The Council has the right to confer Ph. D. degree in physics.
Regina Bąk M.Sc. Institute of Atomic Energy
Waldemar Biłous Ph.D. Institute of Atomic Energy
GraŜyna Birnbaum M.Sc. Institute of Atomic Energy
Prof. Mieczysław Budzyński Ph.D., D.Sc. Maria Curie-Skłodowska University, Lublin
Ewa Byszewska-Szpocińska Ph.D. Institute of Atomic Energy
Prof. Andrzej Czachor Ph.D., D.Sc. Institute of Atomic Energy
Prof. Ludwik Dąbrowski Ph.D., D.Sc. Institute of Atomic Energy
Prof. Ludwik Dobrzyński Ph.D., D.Sc. Soltan Institute for Nuclear Studies
Prof. Roman Wacław Domański Ph.D., D.Sc. Warsaw University of Technology
Natalia Golnik Ph.D., D.Sc. Institute of Atomic Energy, Warsaw University of Technology
Ludwik Górski Ph.D. Institute of Atomic Energy
Zbigniew Haratym Ph.D. Institute of Atomic Energy
Janusz Jaroszewicz M.Sc. Institute of Atomic Energy
Prof. Kazimierz Jeleń Ph.D., D.Sc. AGH University of Science and Technology, Kraków
Edward T Józefowicz Ph.D., D.Sc. Institute of Atomic Energy
Grzegorz Krzysztoszek M.Sc. Institute of Atomic Energy
Prof. Tadeusz Kulik Ph.D., D.Sc. Warsaw University of Technology
Robert Lipka Ph.D. Institute of Atomic Energy
Anna Listkowska M.Sc. Institute of Atomic Energy
Krzysztof Małetka Ph.D. Institute of Atomic Energy
Henryk Michałowski M.Sc. Institute of Atomic Energy
Mieczysław Mielcarski Ph.D., D.Sc. Institute of Atomic Energy
Prof. Janusz R. Mika Ph.D., D.Sc. Warsaw Management Academy
Bogumiła Mysłek-Laurikainen Ph.D. Institute of Atomic Energy
Prof. Jan Pluta, Ph.D., D.Sc. Warsaw University of Technology
Cezary Pochrybniak Ph.D. Institute of Atomic Energy
8 ANNUAL REPORT 2007 General Information
Kielce University of Technology, Warsaw University of Prof. Mieczysław E. Poniewski Ph.D., D.Sc. Technology Prof. Bronisław Słowiński Ph.D., D.Sc. Institute of Atomic Energy, Warsaw University of Technology
Dariusz Socha Ph.D. Institute of Atomic Energy
Joanna Staniszewska M.Sc. Institute of Atomic Energy
Prof. Jan Suwalski Ph.D., D.Sc. Institute of Atomic Energy
Marcin Szuta Ph.D., D.Sc. Institute of Atomic Energy
Tomasz Szyszko vel ChorąŜy Ph.D. Institute of Atomic Energy
Jan Wasiak Ph.D. Institute of Atomic Energy Institute of Nuclear Physics, Polish Academy of Sciences, Prof. Tadeusz Wasiutyński Ph.D., D.Sc. Kraków Prof. Roland Wiśniewski Ph.D., D.Sc. Institute of Atomic Energy
Wioletta Wojdowska Ph.D. Institute of Atomic Energy
Tadeusz Wójcik Ph.D. National Atomic Energy Agency, Warsaw
Edyta Oonk M.Sc. Institute of Atomic Energy
Prof. Mieczysław Zielczyński Ph.D., D.Sc. Institute of Atomic Energy
Chairman of the Scientific Council: Prof. Janusz R. Mika Ph.D., D.Sc. Deputy chairmen: Prof. Andrzej Czachor Ph.D., D.Sc, Mieczysław Mielcarski Ph.D., D.Sc. Secretary: Bogumiła Mysłek-Laurikainen Ph.D. Deputy secretary: GraŜyna Birnbaum M.Sc.
9 General Information ANNUAL REPORT 2007
SCIENTIFIC STAFF
PROFESSORS
Stefan Chwaszczewski, Ph.D., D.Sc. nuclear power and safety Andrzej Czachor, Ph.D., D.Sc. solid state physics Ludwik Dąbrowski, Ph.D., D.Sc. solid state physics Dariusz Mączka, Ph.D., D.Sc. solid state physics, nuclear physics Józef Parus, Ph.D., D.Sc. radiochemistry, radiometric analysis Bronisław Słowiński, Ph.D., D.Sc. nuclear and radiation physics Jan Suwalski, Ph.D., D.Sc. solid state physics Roland Wiśniewski, Ph.D., D.Sc. high pressure physics Mieczysław Zielczyński, Ph.D., D.Sc. radiation dosimetry
ASSOCIATE PROFESSORS
Natalia Golnik, Ph.D., D.Sc. health physics, dosimetry Ewa Hajewska, Ph.D. metallurgy, corrosion of metals Andrzej Hofman, Ph.D., D.Sc. materials science Edward Iller, Ph.D., D.Sc. process engineering, radiochemistry Joanna Michalik, Ph.D., D.Sc. radiopharmacy Mieczysław Mielcarski, Ph.D., D.Sc. nuclear chemistry Kazimierz Mikke, Ph.D. solid state physics Edward T. Józefowicz, Ph.D., D.Sc. reactor safety, radiation protection Rościsław Kaczorowski, Ph.D., D.Sc. nuclear physics Witold Szteke, M.Sc. metallurgy, welding Marcin Szuta, Ph.D., D.Sc. reactor physics Krzysztof Wieteska, Ph.D., D.Sc. solid state physics Zbigniew I. Woźnicki, Ph.D., D.Sc. numerical analysis
10 ANNUAL REPORT 2007 General Information
SENIOR RESEARCHERS
Krzysztof Andrzejewski, Ph.D. reactor physics Waldemar Biłous, Ph.D. materials science ElŜbieta Borek-Kruszewska, Ph.D. nuclear energy and heat exchange Mieczysław Borysiewicz, Ph.D. applied mathematics and system reliability analysis Ryszard Broda, Ph.D. radionuclides metrology Witold Bykowski, Ph.D. reactor engineering Ewa Byszewska-Szpocińska Ph.D. biochemistry, radioimmunology Izabela Cieszkowska Ph.D. nuclear chemistry Piotr Czerski, Ph.D. nuclear power and safety Izabela Fijał-Kirejczyk, Ph.D. solid state physics Ludwik Górski, Ph.D. solid state physics Zbigniew Haratym, Ph.D. gamma spectrometry Joanna Jankowska-Kisielińska, Ph.D. solid state physics Henryk Jędrzejec, Ph.D. nuclear physics Krystyna Józefowicz, Ph.D. radiation metrology Teresa Kulikowska, Ph.D. reactor physics Janusz Licki, Ph.D. new technology and engineering Robert Lipka, Ph.D. radiochemistry Krzysztof Małetka, Ph.D. nuclear physics Zuzanna Marcinkowska, Ph.D. reactor physics Jan K. Maurin, Ph.D. solid state physics Renata Mikołajczak, Ph.D. radiopharmacy Jacek J. Milczarek, Ph.D. solid state physics Bogumiła Mysłek-Laurikainen, Ph.D. radioecology Beata Paluchowska, Ph.D. solid state physics Cezary Pochrybniak, Ph.D. solid state physics Sławomir Potempski, Ph.D. computer science and numerical analysis Krzysztof Pytel, Ph.D. reactor physics Zdzisław Rusinowski, Ph.D. radiation metrology Dariusz Socha, Ph.D. radiopharmacy Agata Stoch, Ph.D. solid state physics Paweł Stoch, Ph.D. solid state physics ElŜbieta Strugarska-Gola, Ph.D. experimental physics, nuclear physics Andrzej Strupczewski, Ph.D. nuclear safety Jan Szczurek, Ph.D. nuclear safety analysis Tomasz Szyszko vel ChorąŜy Ph.D. nuclear chemistry
11 General Information ANNUAL REPORT 2007
Katarzyna Tymińska, Ph.D. nuclear physics Jan Wasiak, Ph.D. materials science Mariusz Wieczorkowski, M.Sc. metallurgy, welding Teresa Wilczyńska-Kitowska, Ph.D. solid state physics Zbigniew Wiśniewski, Ph.D. solid state physics Andrzej Wojciechowski, Ph.D. computer science and numerical analysis Wioletta Wojdowska, Ph.D. nuclear chemistry Piotr Zachariasz, Ph.D. solid state physics
RESEARCHERS
Marcin Bielewicz, M.Sc. nuclear physics Ilona Garanty, M.Sc. computer science and numerical analysis Michał Gryziński, M.Sc. radiation dosimetry Barbara Janota M.Sc. radiopharmacy, peptides chemistry Anna Kozubal, M.Sc. computer science and numerical analysis Magdalena Mądry, M.Sc. nuclear chemistry Jakub Ośko, M.Sc. biomedical engineering Beatrycze Pytel, M.Sc. reactor physics Piotr Tulik, M.Sc. biomedical engineering
FINANCES AND PERSONNEL
1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007
Total revenues (MPLN) 17.3 20.0 21.4 22.4 20.3 17.9 17.6 16.0 18.4 18.8 35.5
Total costs (MPLN) 20.7 22.6 23.2 23.4 20.2 18.2 17.5 16.5 18.4 18.9 36.9
Total profit/loss (MPLN) -3.4 -2.6 -1.8 -1.0 0.1 -0.25 0.1 -0,5 0 -0.1 -1.4
Investments (MPLN) 2.2 1.4 0.6 0.8 1.3 2.1 5.6 6.6 6.0 8.1 11.4
Total number of employees 445 403 375 353 288 267 269 275 275 275 443
12
ANNUAL REPORT 2007 Operation and Safety of Maria Reactor
OPERATION OF THE MARIA RESEARCH REACTOR G. Krzysztoszek, A. Gołąb, J. Jaroszewicz Institute of Atomic Energy The multipurpose high flux research reactor reflector made of graphite blocks in aluminum cans. MARIA is a water and beryllium moderated reactor of a The MARIA reactor is equipped with vertical channels pool type with graphite reflector and pressurized chan- for irradiation of target materials, a rabbit system for nels containing concentric six-tube assemblies of fuel short irradiations and six horizontal neutron beam chan- elements. It has been designed to provide high degree of nels. The main elements of the reactor pool are pre- flexibility. The fuel channels are situated in a matrix sented in Fig. 1. containing beryllium blocks and enclosed by lateral
1 2 3 4
+5.0
5 9 6 7 10 8
H3, H8 - 135 cm H7 - 115 cm -1.7 H4, H5, H6 - 95 cm
11 12 13 14
Fig. 1. Vertical section of MARIA reactor. 1. control rod drive mechanism, 2. mounting plate, 3. ionisation chamber channel, 4. ionization chamber drive mechanism, 5. fuel and loop channels support plate, 6. plate support console, 7. horizontal beam tube shutter drive mechanism, 8. beam tube shutter, 9. fuel channel, 10. ionization chamber shield, 11. core support structure, 12. core and reflector support plate, 13. reflector blocks, 14. beam tube compensation joint.
The main characteristics and data of MARIA reac- - enrichment 36% tor are as follows: - cladding aluminium - shape six concentric tubes nominal power 30 MW(th), - active length 1000 mm. thermal neutron flux density 4.0·1014 n/cm2s, output thermal neutron flux moderator H O, beryllium, 2 at horizontal channels 3÷5x109 n/cm2s cooling system channel type, fuel assemblies: The MARIA reactor reached its first criticality in - material UO2-Al alloy December 1974. The reactor was in operation until 1985 15 Operation and Safety of Maria Reactor ANNUAL REPORT 2007
when it was shut down for modernization. The mod- - irradiation of target materials in vertical channels ernization encompassed refurbishment and upgrading of and in rabbit system, technological systems. In particular, the efficiency of - neutron scattering experiments using neutron beams ventilation and cooling systems was improved. In 1993 from reactor horizontal channel, the MARIA reactor was put into operation again. - neutron radiography research at the horizontal channel H8, The main areas of reactor application are: - neutron modification of crystals and minerals. - production of radioisotopes, - testing of fuel and structural materials for nuclear At present only MR-6 type fuel assemblies with power engineering, 36% enrichment and 430g contents of U-235 are loaded - neutron radiography, in the reactor core. The release of fission products from - neutron activation analysis, this fuel is very low and achievable burn-up is above - neutron transmutation doping, 50%. - research in neutron physics. The core configuration has been changed several In 2007 the reactor completed 40 operation cycles times because of fuel and irradiation requirements. The at power levels from 30 kW to 20 MW (Fig. 2). The core configuration of December 2007 (Fig.3) consisting overall operation time was 4002 h. of 17 fuel assemblies-main core and 7 fuel assemblies in the lateral row was due to the needs of irradiation of The main activities carried out in MARIA reactor minerals under special neutron flux conditions. were focused on:
Fig. 2. Schedule of the reactor MARIA operation in 2007.
16 ANNUAL REPORT 2007 Operation and Safety of Maria Reactor
Fig. 3. Core configuration of December 2007.
364 spent fuel assemblies have been collected dur- Operational availability factors were: ing many years of reactor operation. The assemblies OT have been stored under water in the special pool adja- A1 = ⋅100% = 98 7. % cent to the reactor pool. To prevent possible damage of NH fuel cladding due to the corrosion processes the assem- OT A2 = ⋅100% = 45 7. % blies are encapsulated in special tight cans filled with 8760 inert gas. The encapsulation technology was developed and implemented in 2002. Until the end of 2007 157 where OT (operational time) denotes the number of fuel assemblies were closed successfully in cans made hours on power and NH is the sum of number of hours of stainless steel. on power and on unscheduled shutdown. The removal of the encapsulated fuel assemblies In 2007 the total emissions of radioactive materials from the reactor fuel storage has been initiated on De- to the environment were as follows: cember 2005. Until the end of 2007 96 encapsulated - inert gases (mainly 41Ar): 1.19·1013 Bq, i.e. 1.2% of fuel assemblies were removed from the reactor storage the limit determined by the NAEA, pool to the temporary wet spent fuel storage. - iodine: 1.37·108Bq, i.e. 2,7% of the limit deter- In 2007 the MARIA reactor was operated success- mined by the NAEA, 88 138 9 fully. Nevertheless the reactor scram was activated 11 - Rb and Cs: 1.87·10 Bq. times. Nine times the reactor was shut down only for a In 2007 99 workers received measurable whole very short time, mainly for the reason of drops in elec- body doses from 0.1 to 3.82 mSv and 8 workers re- trical power supply system and malfunction of the reac- ceived skin doses from 0.65 to 5.34 mSv. tor instrumentation system. Two reactor scrams caused The electrical conductivity and pH value of water shortening of the operation cycles: in the main reactor systems were controlled perma- - first due to a leakage in the primary cooling system, nently (Fig. 4, 5). - second due to malfunction of transducer in the main pump supplying system. 17 Operation and Safety of Maria Reactor ANNUAL REPORT 2007
4
Inventory tank Fuel channels Storage pool Reactor pool
3
2 Conductivity mS/cm
1
0 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45
Number of measurement
Fig. 4. Conductivity of water in the primary circuits of the reactor Maria in 2007.
Inventory tank Fuel channels
6,5 Storage pool Reactor pool pH value 5,5
4,5 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 Number of measurement
Fig. 5. pH value of water in the primary circuits of the reactor Maria in 2007.
New technology - neutron irradiation services quired neutron flux levels, irradiation times, target mass and size. Neutron irradiation services utilizing MARIA research reactor include radioisotope production, neutron trans- The vertical in-core isotope channels were consid- mutation doping of silicon, neutron activation analyses ered as a design requirements for high activity radioiso- and biomedical technology. topes production as well as the modernized hydraulic Available services cover the activation of a large transfer system. For the domestic customers the targets variety of target materials for the production of isotopes of S, TeO2, Lu2O3, Yb2O3, Cu, Se, SmCl3 and KCl were which would subsequently be processed at the discre- irradiated (Fig. 6). tion of the customer. For irradiation services various Most of the radioisotopes were produced for the systems are available in the MARIA reactor, providing Isotope Research and Development Center POLATOM. necessary irradiation conditions according to the re- Among the new approaches developed for radioisotopes of current interest in nuclear medicine and industry were
18 ANNUAL REPORT 2007 Operation and Safety of Maria Reactor
iridium seed-targets. The source wire in each seed was Neutron irradiation service utilizing reactor made of platinum - iridium alloy. The Ir-192 seeds used MARIA includes the coloring of topaz minerals. The in Intravascular Radiation Therapy (IRT) and low activ- irradiation of minerals in special channels located out- ity Ir-192 ribbon for oncology applications were pro- side reactor core change its colorless transparent natural duced. state to shades of blue, thereby increasing the commer- cial value of the product. After appropriate cooling time The irradiation services offered at MARIA re- the blue minerals are released to the market as the non- search reactor include the Neutron Transmutation Dop- radioactive material. ing (NTD) of silicon crystals. High purity silicon single crystals are doped to produce n-type semiconductor Feasibility study on irradiation of 235U targets in material. The NTD is based on the transmutation of 30Si the MARIA reactor for 99Mo production has been atoms into 31Si by the capture of thermal neutrons. The started in 2007. The main objective is to obtain the 31Si decays by the emission of beta particles to 31P. The 99mTc isotope, which is widely used in the medical diag- results of experimental irradiation of silicon ingots of 5” nostics. The decisive factor determining its availability, and 6” diameter confirmed good quality of neutron despite its short life time, is the radioactive decay of doped silicon crystals. The uniform neutron dose distri- 99Mo into 99mTc. One of the possible sources of molyb- bution over the ingot ensures the homogeneous distribu- denum can be achieved within the 235U fission reaction. tion of phosphorous atoms throughout the silicon crys- Currently 99Mo is produced by most producers by irra- tal, resulting in uniformly doped n-type silicon matching diation of HEU targets. The new idea that conforms to the electrical resistivity needed. The axial and radial the Reduced Enrichment for Research on Test Reactors resistivity variation of the sample is controlled to satisfy (RERTR) program is to use LEU-foil targets. Technol- the customer needs. At present the facility installed in ogy for production of 99Mo is based on the core loop the poolside region of the reactor is ready for commer- which consists of standard fuel channel supplemented cial neutron transmutation doping of silicon ingots for with necessary control units. Toshiba Ceramics. The range of irradiation services offered using the test facility was extended by transmu- tation doping of multicrystalline silicon wafers for photovoltaic cells.
1200
1100 other biological materials 1000 lutetium minerals 900 potasium chloride xenon 800 iridium cobalt 700 molibdenum tellurium 600 samarium sulphur 500
400 Number of the containers Number irradiated
300
200
100
0
5 6 7 8 99 00 01 02 03 004 005 006 1978 1979 1980 1981 1982 1983 1984 1985 1993 1994 199 199 199 199 19 20 20 20 20 2 2 2 2007
Year
Fig. 6. Distribution of target materials irradiated.
19 Operation and Safety of Maria Reactor ANNUAL REPORT 2007
UPGRADE OF MARIA REACTOR MODEL FOR OPERATIONAL PREDICTIONS IN 2007 K. Andrzejewski, T. Kulikowska, Z. Marcinkowska Institute of Atomic Energy The development of computational capabilities and permanent need for predicting the reactor MARIA oper- 1500 ating conditions lead to the upgrading of the existing methods for MARIA core neutron-physics analysis. .
In 2007 a full description of the MARIA reactor 1000 core has been completed [1], including the special pur- pose channels and blocks. On the basis of this descrip- tion the models developed in the REBUS code have
Energia pomiar [MWh] 500 been extended. The present model accounts for: Measured burn-up [MWh] − initial fuel element material composition given in 0 fuel certificates, 0 500 1000 1500 − CalculatedEnergia REBUS burn-up [MWh] [MWh] individual fuel element burnup history, − 15 types of geometry of beryllium blocks, Fig. 1. Calculated vs. measured burn-up level of fuel elements, − individual beryllium block transmutation history, old model. Light green points correspond to fuel chan- − special purpose channels and blocks including nels neighboring to isotope channels, dark green – close to absorbing filters, green – the others. irradiation channel, − control and safety rods with their operational posi- tions in 3D calculations, − core reflectors. 1500
The computations are performed using current data . on the core configuration, reactor power, control rods position and materials temperatures. 1000 Computational results are routinely compared to the measured data on reactivity change with fuel burnup and transmutations in beryllium (weekly and annually), Energia pomiar [MWh] 500 control rod worth, temperature reactivity coefficients.
The analysis of the burnup level of particular fuel Measured burn-up [MWh] 0 elements [2] resulted in the corrections of geometrical 0 500 1000 1500 representation of irradiation channels and absorbing CalculatedEnergia REBUS burn-up [MWh] [MWh] filters. Without corrections marked differences between the calculated and measured burnup level are observed Fig. 2. Calculated vs. measured burn-up level of fuel elements, (Fig. 1). The corrections improved the compatibility of new model. The description of points is the same as in Fig. 1. the calculation results of the new model with the meas- ured fuel burnup of fuel elements (Fig. 2). Three new auxiliary programs [4] have been devel- Further analysis carried out together with Argonne oped to facilitate REBUS input preparation. National Laboratory [3] under the RERTR cooperation, The computational model has been used in predic- has shown the effects of: tion of the reactivity change of planned beryllium − application of burnup dependent library of REBUS blocks reloading. Block from position I-VII is going to for MARIA fuel elements gives improvement of be exchanged with that at K-IX, and H-VII with that at about 2% in keff, K-V. − introduction of axially dependent burnup gives up References to 1% improvement in keff. [1] K. Andrzejewski, T. Kulikowska, Z. Marcinkowska, Raport IAE-129/A (2007) [2] K. Andrzejewski, T. Kulikowska, Z. Marcinkowska, (in Polish), IAE Report B-5 (2007) [3] N. Hannan, Private communication, (2007) [4] K. Andrzejewski, T. Kulikowska, Z. Marcinkowska, IAE Report B-7 (2007)
20
ANNUAL REPORT 2007 Radiation Protection and Dosimetry
THE ACTIVITIES OF THE RADIATION PROTECTION MEASUREMENTS LABORATORY B. Filipiak, N. Golnik, Z. Haratym, E. T. Józefowicz, K. Józefowicz, T. Pliszczyński, B. Snopek Institute of Atomic Energy The Radiation Protection Measurements Labora- The research activities of Laboratory are described tory (RPML) of the Institute of Atomic Energy is re- on the next pages of the Annual Report. sponsible for handling all the problems concerning The technical activities of the RPML in 2007: radiation protection at the Institute and in the vicinity of - Whole body (WBC), thyroid (TC) and “in vitro” Nuclear Centre (NC) Świerk and National Repository of (RL) monitoring were carried out for radiation Radioactive Waste (NRRW) at RóŜan. workers from NC Świerk and external customers: The main tasks of RPML are: 392 WBC, 161 TC and 170 RL measurements were - Radiation monitoring of the Świerk and RóŜan made in 2007 (Tables 1- 3). The collected results of sites. measurements of 137Cs internal activity in people, - Surveillance of radiation safety. from 1986 and 2007, are presented in Fig. 1. - Radioactive waste control. - Regular monitoring of radiation workers was car- - Radiation protection in emergency conditions. ried out with TLD dose meters. Values of individual - Improvement of radiation protection measurements dose equivalents registered are below the annual and methods. dose limit. - Calibration of radiation protection monitoring in- - The environmental monitoring within or outside the struments. NC and NRRW boundaries included the measure- - Personal dosimetry. ments of direct or stray radiation due to the opera- - Sewage and drainage water activity measurements. tion of reactors, accelerators, etc. and the measure- - Environmental radiation monitoring. ment of radioactivity in samples of air, rivers’ and underground water, soil, sediment, mud and vegeta- The following laboratories and facilities are avail- tion. In 2007 more then 1000 environmental sam- able in the Laboratory: ples were measured (Tables 4-6). - Mixed radiation fields laboratory (MRF). - Whole body counter (WBC). Table 1. Whole body counter measurements. - Counter of thyroid activity (TC). Dose measurements persons - Calibration laboratory with standard radiation sources (Calibration Division, CD). < 1% EW 392 282* > 1% E - - - Environmental measurements laboratory. W - Radiochemical laboratory (RL). Total 392 282 On December 31, 2007 the Laboratory employed * - 37 persons were contaminated by iodine 131 including 19 per- sons measured by Thyroid Counter and calculated the committed 19 graduate staff members and 9 non graduated. dose equivalent. In 2007 RPML continued successfully the activi- Ew – limit of annual effective dose. ties concerning improvement of measurement proce- Table 2. Thyroid counter measurements. dures in two main domains of Laboratory accredited by the Polish Centre for Accreditation (PCA): Dose - The determination of internal body contamination Measurements Persons < 1% EW > 1% EW (whole body, thyroid and excretions) – accreditation Total 161 32 24 8 No. AB 567. Table 3. Measurements of biological probes. - Calibration of dosimetric instruments (gamma, neutron and surface contamination monitors) – ac- Measure- Persons <1% EW >1% EW ments creditation No. AP 070. Total α-activity 2 2 2 - The improved versions of Quality Manual as well Total β-activity 126 103 103 - as all the procedures were completed and some techni- Activity of P-32 9 6 6 - cal and organizational activities undertaken, especially Activity of S-35 7 5 5 - concerning validation, traceability and estimation of Activity of tritium (HTO) 23 19 19 - uncertainties of the methods used. Activity of Sr-90 3 3 3 - Several internal quality audits were performed, The results of performed measurements indicate opinions collected from experts, and in March 2007 the that there is no contamination of the environment and yearly PCA audit took place for AB 567 and in Septem- the human population in the vicinity of the NC and ber 2007 for AP 070, both with positive results. NRRW.
23 Radiation Protection and Dosimetry ANNUAL REPORT 2007
2000 Woman 800
1750 Men 700 1500 LDA 600
1250 500
1000 400 750 300
500 200 250 100 Total body activity from 1993
Total body activity till end of 1992 0 0 Q2 Q2 1986 Q2 1987 Q2 1988 Q2 1989 Q2 1990 Q2 1991 Q2 1992 Q2 1993 Q2 1994 Q2 1995 Q2 1996 Q2 1997 Q2 1998 Q2 1999 Q2 2000 Q2 2001 Q2 2002 Q2 2003 Q2 2004 Q2 2005 Q2 2006 Q2 2007
Time
Fig. 1. The activity of 137Cs in people after the Chernobyl accident (mean per person).
Table 4. Total activity of β-radiation of water samples from inside and outside of the – NRRW RóŜan in 2007. Average Concentration [Bq/dm3] Type of probe and place of Number value min max medium collection of probe 2006 2007 2007 2007 Ground waters 10p 0,09 < 0,08 0,15 0,10 Inside of NRRW RóŜan 11p 0,16 < 0,08 0,20 0,13 12p 0,29 < 0,08 0,29 0,18 17p 0,12 < 0,08 0,34 0,16 18p < 0,08 < 0,08 0,10 0,09 131 0,54 0,60 0,74 0,66 Tap water (inside NRRW) F-R 0,11 < 0,08 0,13 0,10
Table 5. Activity of tritium (HTO) in water samples from inside and outside of the NRRW RóŜan in 2007. Type of probe and place of Number of Average value Concentration of trytium [Bq/dm3] collection probe 2006 I Q 2007 II Q 2007 III Q 2007 IV Q 2007 Ground waters 10p < 4,0 < 4,0 < 4,0 19 7,0 Inside of NRRW RóŜan 11p 310 240 250 320 320 12p 3700 2400 1600 3000 1400 17p 680 680 580 660 620 18p < 4,0 < 4,0 10 15 5,0 130p 180 220 220 21 240 131p 16000 16000 14000 16000 18000 132p 43 < 4,0 8,0 260 380 Ground waters F-1 24 10 36 42 27 Outside of NRRW RÓśAN Tap water (inside NRRW) F-R < 4,0 < 4,0 < 4,0 26 < 4,0
24 ANNUAL REPORT 2007 Radiation Protection and Dosimetry
Table 6. Activity of environmental samples (soil and grass) from inside and outside the NRRW RóŜan in 2007 [Bq/kg].
Type of probe Place K-40 Cs-137 Ac-228 Ra-226 and place of collection (Th-232) (U-238) Soil - II quarter inside G 706 350 6,4 11 10 707 570 450 18 12 outside 701 640 34 22 20 703 470 58 17 10 Soil - III quarter inside G 706 400 50 17 20 707 510 400 11 15 outside 701 640 68 21 22 703 350 3,2 10 15 Grass - II quarter inside R 706 800 10 < 7,0 < 3,0 R 707 790 5,5 < 7,0 < 3,0 outside R 701 920 2,0 < 7,0 < 3,0 R 703 950 < 1,0 < 7,0 < 3,0 Grass - III quarter inside R 706 1200 < 1,0 < 7,0 < 3,0 R 707 1100 12 < 7,0 < 3,0 outside R 701 430 3,2 < 7,0 < 3,0 R 703 920 1,5 < 7,0 < 3,0
The Calibration Laboratory is maintaining and us- Calibration Laboratory performs calibrations of ing the standard fields of neutron and gamma radiation. surface contamination monitors, using reference sources The 137Cs is the main calibration source of gamma ra- of beta and alpha radiation. In 2007 a new standard diation. Standard neutron fields, traceable to primary source 36Cl for contamination monitors was introduced standard laboratory National Physical Laboratory (NPL, for routine use. Great Britain) were established at the Institute of Total number of monitors calibrated in 2007 was: Atomic Energy (IAE) ten years ago. The fields are - Surface contamination monitors - 107 formed by calibrated sources of 252Cf and 241Am-Be. For - Gamma dose and dose rate monitors - 150 routine use, there is also 239Pu-Be neutron source avail- - Neutron dose equivalent monitors - 7 able calibrated against standard source of 241Am-Be. Additionally, spherical filters made of iron or paraffin In 2007 the staff of CD performed the periodical can be applied for modification of the neutron spectrum tests of dosimetric monitoring system of MARIA reac- and gamma component of absorbed dose. tor as well as the calibration of data lines of the system with the detectors. The neutron sources are used mostly for research purposes. However, since they form the only standard The calibration of radiation monitors in liquid ra- neutron fields in Poland, they are employed for calibra- dioactive waste storage tanks of Radioactive Waste tion of neutron dose meters used in radiation protection. Management Plant was performed as well as the calibra- Maintenance of the fields includes periodic assessment tion of radiation monitoring personal gate. of the dosimetric parameters, development of measuring methods and international interlaboratory comparisons. The parameters of neutron fields in the IAE calibration hall have been periodically checked. In 2006 the Labo- ratory participated in International Neutron Intercom- parison EUROMET Project No 608. The preliminary results of the comparison were disclosed in 2007. In the field of 137Cs gamma source the periodical check measurements were performed applying specially designed and constructed reference instrument. The kerma rate in gamma radiation fields of new gamma irradiator were measured by Central Office of Measures. The complementary tests with Laboratory own refer- ence instrument, have started. 25 Radiation Protection and Dosimetry ANNUAL REPORT 2007
DETERMINATION OF INITIAL RECOMBINATION OF IONS CREATED IN QUASI-PULSED RADIATION FIELDS M. Zielczyński, N. Golnik, M.A. Gryziński Institute of Atomic Energy There are two main recombination processes influ- For pulse radiation, the ion collection efficiency encing the ion collection efficiency in high pressure fvp , can be approximated by similar formula: ionization chambers – initial recombination and volume 1 recombination. f = vp + 1 bvi / U Initial recombination occurs between oppositely charged ions from the same track of a charged particle. Both coefficients, av and bv, depend on the distance It dominates at gas densities of several kg/m3, electrical between electrodes in the chamber and the gas parame- field strength above 1 kV/m and the absorbed dose rate ters. For given ionization chamber, av and bv are con- in the gas below ca. 1 Gy/h. stant. The coefficient av can be determined from the measurements of ion collection efficiency at different Volume recombination occurs between ions from dose rates in a steady radiation field [3]. Similar proce- different tracks formed by ionizing particles. It depends dure can be performed in order to determine the con- on the measured current, i, hence on the absorbed dose stant bv in a pulse radiation field. rate in the gas cavity. It is independent neither of LET, ionization particle energy nor of other parameters de- In the case of quasi-pulsed fields when the ion col- scribing the radiation quality. This kind of recombina- lection time and the pulse repetition time are of the tion is a dominant process of ion recombination at high same order of magnitude or when both the steady and dose rates, in ionization chambers with large distance the pulse components are present none of the above between electrodes and at low gas density. The cham- equations is correct. bers with smaller distance between electrodes can oper- In our approach [4], we assume that the ion collec- ate at higher dose rates, or at lower voltages. tion efficiency in the volume recombination process, has Initial recombination occurs in very short time after the form formation of the charged particle track, until the ions = 1 diffuse to the distance of few hundreds nanometers. The f v 1+ i / F()U volume recombination is present all the time of ion collection in the chamber. The initial and volume re- where F(U) is an unknown function of the voltage U. combination are the consecutive processes, i.e. the ions Then, the ion collection efficiency f(U) should be that recombine through volume recombination are those determined for two different dose rates of investigated which have avoided the initial recombination. radiation, without changing its time structure. The dose The ion collection efficiency in an ionization rates should grant the negligible volume recombination chamber can be expressed as the ptoduct: at highest voltage applied to the chamber. Combining the first and the last of the above equations, one can get = ⋅ ⋅ f fi fv fk two equations for two values of i, with two parameters – where fi and fv are ion collection efficiencies of local F and fi to be calculated, for each voltage U. No detailed and volume recombination, respectively, fk is the correc- information is needed about the time structure of radia- tion factor for other effects including back diffusion of tion. ions, radiation background, leakage current, and temperature effects. References For steady radiation and given polarizing voltage [1] N. Golnik, Raport IAE–20/A (1996) U, the ion collection efficiency in the volume recombi- [2] J.W. Boag, in: Attix, F. M. Roesch, W. C. (eds.), Radia- tion dosimetry, II, Acad. Press, (1968) nation process, fvs , can be expressed as [2]: [3] M.A. Gryziński et al., Nukleonika, 52(1) 7 (2007) 1 [4] N. Golnik et al., Nucl. Instr. and Meth. A 580 25 (2007) f = vs + 2 1 avi /U
26 ANNUAL REPORT 2007 Radiation Protection and Dosimetry
NEUTRON-TO-GAMMA SENSITIVITY RATIO OF THE RECOMBINATION CHAMBER AS A FUNCTION OF NEUTRON ENERGY N. Golnik, M. Zielczyński Institute of Atomic Energy Relative neutron sensitivity of the REM-2 chamber 2.0 (versus reference gamma radiation) was determined from the measurements of saturation current in almost monoenergetic neutron fields with energies ranging 1.5 from 75 keV to 19 MeV. The measurements were per- h formed in the low-scatter environment of the Physi- 1.0 kalisch Technische Bundesanstalt (PTB, Braunschweig, Germany) accelerator facility [1]. A De Pangher preci- sion long counter and a 3He detector served as neutron 0.5 monitors. In addition, the beam charge collected on the target was continuously monitored. 0.0 The REM-2 chamber was positioned at a distance 0.1 1 10 100 of 2.5 m from the target. The reading of the chamber E [MeV] was normalized to the beam charge.
The photon dose fraction of the mixed neu- Fig. 1. Dependence of the relative neutron sensitivity to D*(10) on neutron energy, for REM-2 chamber. tron/photon fields was determined with a Geiger-Müller (GM) counter (type ZP1100). The photon contribution We found [4] that the REM-2 chamber calibrated to the absorbed dose was below 2% for all neutron with the 137Cs source, overestimates the D*(10) values fields with nominal energies greater than 0.6 MeV. for neutrons of 0.05-4 MeV and in high energy region The measurements in high-energy neutron fields (Fig. 1). The effect at lower energies is due to higher were performed at CERF facility in CERN. The beam, content of hydrogen in the gas in the chamber than it is of 120 GeV/c positively charged particles (protons and in tissue. The influence of the gas composition becomes pions extracted from the SPS accelerator) was directed less important at higher energies and the overestimation onto a copper target. The target was placed either in the is caused mainly by higher contents of carbon and lower position under a 40 cm thick iron roof shield (called iron content of oxygen in tissue equivalent material, com- position) or under an 80 cm thick concrete roof shield pared to tissue. (called concrete position). The beam was shielded from At the energies around 14 MeV, there is a narrow the side by a concrete wall with the thickness of 80 cm minimum in the relative neutron sensitivity of the for the concrete position and of 160 cm for the iron chamber. The lowest value of h = 0.76 was recorded for position. The time characteristic of the field revealed the 14.8 MeV neutrons but the range of neutron energies pulse structure of the beam with the duration time of 2 s where h is considerably below 1 is narrow and the influ- and repetition time of 14.4 s. Beam intensity was moni- ence of the region on the results of the measurements in tored with a Precision Ionization Chamber (PIC) in the high energy radiation fields is usually very small or beam line located at the end of the beam pipe upstream negligible. of the target positions. The reference values of H*(10) are based on calculations and evaluated results of the intercomparisons [2]. References [1] H. J. Brede et al., Nucl. Instrum. and Meth., 169 349 Measurements were performed also in frame of the (1980) EURADOS benchmark experiment at Gesellschaft für [2] M. Höfert, G. R. Stevenson, Report CERN/TIS- Schwerionenforschung (GSI, Darmstadt, Germany). RP/IR/94-02, CERN, Geneva, 1994 Beam of 12C ions with a specific energy of 400 MeV/u [3] H. Iwase et al., Radiat. Prot. Dosim., 116 640 (2005) and intensity of 2·109 ions per spill was delivered by the [4] N. Golnik, M. Zielczyński, IEEE Nuclear Science Sym- posium and Medical Imaging Conference, Honolulu, heavy-ion synchrotron SIS-18 to the experimental area Hawaii, USA, October 27 – November 3, 2007, N39-3 at Cave A. The measurement position, marked as OC-10 [3], was in forward direction to the target position, be- hind a 160 cm thick concrete shield. The preliminary H*(10) values, determined with the Bonner sphere spec- trometer NEMUS, by PTB group, were used here as the reference values.
27 Radiation Protection and Dosimetry ANNUAL REPORT 2007
MONTE CARLO CALCULATION OF NaI DETECTOR FOR IODINE 131I IN THYROID J. Ośko, N. Golnik Institute of Atomic Energy The aim of our work was to calculate the iodine The calculated and measured radiation spectra for 131I radiation spectrum registered by NaI(Tl) detector 23 mm thyroid depth are similar except the height of the during measurement of iodine 131I source immersed in 30 keV energy peak (Fig. 1). Since this part of spectrum the water thyroid phantom. is not used in determination of the iodine activity, the difference is not of practical importance. The calculations were carried out for the thyroid phantom used in Radiation Protection Measurements The method for calibration of the thyroid counter Laboratory for thyroid counter calibration. The thyroid with 131I used in Radiation Protection Measurements location inside the phantom can be altered in vertical Laboratory takes into account the position of the thyroid and horizontal plane [1]. The results of the 131I radiation inside human neck. The thyroid depth is determined spectrum simulation can serve as an assessment of the using parameter S defined as the ratio of the 364 keV implementation of changes into the testing equipment. counts and number of counts in the spectrum region of Compton scattering photons. This region is 100- Our calculations were performed with the Monte 150 keV (S ) or 110-140 keV (S ). The results of the Carlo “Penelope” code using the appropriate modifica- 1 2 calibration process are two curves: values of the pa- tion of “Penmain” program [2]. The modelled detector rameter S versus the thyroid depth and values of detec- consists of cylindrical scintillator plate (40 mm diame- tion efficiency versus parameter S [1]. ter, 25 mm height) contained within 1 mm thick alumin- ium sheath (46 mm diameter, 32 mm height). The space The Monte Carlo calculations were carried out for between the scintillator and the wall is filled with Al2O3 six different values of thyroid depth. The calculated S1 powder. Detector is sheltered with the cone shaped lead and S2 parameters agree to those determined experimen- collimator. The spherical 131I source was placed in cyl- tally (Fig. 2). inder which was modelled as tissue and water. The 2,5 results of measurements of iodine source in the water thyroid phantom and in the human neck should be com- 2 parable. 1,5 Experimental
S Calc. - tissue 1 Calc. - water 0,5
0 20 30 40 50 60 70 80 thyroid depth [mm]
Fig. 2. The values of parameter S1 (lower curve) and S2 (upper curve) versus thyroid depth determined from measure- ments and calculations results. 2,50E-08
2,00E-08 Our results indicate that the Monte Carlo model 1,50E-08 can be used for pre-calibration research and the water 1,00E-08 thyroid phantom is a good model for the gamma ray
5,00E-09 absorption and scattering in human neck.
0,00E+00 S1 1
25 49 73 97 121 145 169 193 217 241 265 289 313 337 361 385 References Fig. 1. The iodine 131I spectrum for thyroid depth 23 mm – [1] J. Ośko et al., Raport IAE-122/A (2005) measured (upper) and calculated (lower). [2] F. Salvat et al., Penelope-2006, Workshop Proc., 4-7 July 2006, Barcelona, Spain
28 ANNUAL REPORT 2007 Radiation Protection and Dosimetry
RELATIVE NEUTRON SENSITIVITY OF IONIZATION CHAMBER FILLED WITH HYDROCARBON GASES M.A. Gryziński Institute of Atomic Energy Neutron sensitivity of the tissue-equivalent ioniza- tion chamber is lower than its sensitivity to gamma radiation. In order to increase the neutron sensitivity, the chamber is filled with a gas mixture containing more hydrogen than the soft tissue. The hydrocarbon gases are suitable for this goal. It is preferable if the ionization chambers, especially the recombination chambers for measurements in mixed radiation fields, have similar sensitivity to gamma and neutron radiation, i.e. the relative neutron sensitivity, hn , is close to unity. The following definition is used [1]:
HN = AN / AC where A = i (U ) / D& is the sensitivity of the chamber n n S n to neutrons with spectrum considered; D& ≡ D*(10) is Fig. 1. Dependence of the relative neutron sensitivity (neu- the ambient absorbed dose rate at the point of measure- trons from 238Pu-Be source) of the REM-2 chamber on ment; and A = i (U ) / D& is the sensitivity to the filling gas density for methane (the upper curve) and C C S C propane (the lower curve). 137 reference gamma radiation ( Cs source). in(US) and i (U ) are ionization currents in neutron radiation field C S The gases with high content of hydrogen (CH4) are and in the reference gamma radiation field measured at most convenient for the high pressure recombination the voltage US respectively. chambers used in mixed radiation fields, because with such gases it is easier to obtain similar sensitivity of the The value of relative sensitivity hn is necessary when the chamber is used for the determination of the chamber to neutron and gamma radiations. However, it ≈ dose components in mixed (neutron + gamma) radiation is not possible to have hn 1 for all neutron energies. field, using the twin-chambers techniques. The second For the REM-2 chamber filled with methane chamber is usually a hydrogen-free chamber with low (p = 1 MPa, US = 1200 V) the hn changes from 0.6 up to 1.5 in the neutron energy range from thermal to relative sensitivity to neutrons. The dependence of hn on gas density was determined [1] using reference radiation 200 MeV. However, in the case of the radiation of un- fields of 137Cs and 239Pu-Be sources and subtracting the known neutron energy, it is preferable to have hn less earlier known contribution of gamma radiation from the energy dependent, even if the value of hn considerably Pu-Be source. differs from unity.
The recombination chamber of REM-2 type with The maximum observed in the dependence of hn on tissue equivalent electrodes was used in the studies. The the gas density (Fig.1) is caused by increasing contribu- chamber of ~1800 cm3 volume and the distance d = 7 tion of directly ionizing particles created in gas to the mm between electrodes was employed. The measure- ionization current, with increasing gas density. The ments were performed with the chamber filled with decrease of hn with increasing density observed at methane, ethane, ethylene or propane up to the pressure higher gas densities is due to the initial recombination of 1.8 MPa. The results are presented in the form of the of ions in tracks formed by ionizing particles produced by neutrons. hn dependence on gas density instead of gas pressure (Fig. 1). References [1] M.A. Gryziński et al., Nukleonika 52 7 (2007)
29 Radiation Protection and Dosimetry ANNUAL REPORT 2007
RELATIVE LOCAL IONIZATION DENSITY – CORRELATIONS WITH MICRODOSIMETRIC PARAMETERS M. Zielczyński, N. Golnik Institute of Atomic Energy Local recombination of ions is the recombination 2. Ratio of the mean lineal energies: which occurs within a column or group of ions created y by one charged particle. This type of recombination µ = ()d occurs a short time after the primary ionization events, yd Cs before the ion column spreads out due to the diffusion The mean chord of the site, d, is in this case of about and ion drift in the electrical field in the detector. The 25 nm, what corresponds to a sphere diameter of about volume recombination may take place afterwards. Local 0.15 µm. The dose mean lineal energy for 137Cs gamma recombination of ions does not depend on the dose rate radiation is about 5 keV/µm. but it does depend on local ionization density in the track of the charged particle, thus it depends on LET, it 3. Ratio of the effective restricted LET of the consid- can therefore be used for determination of the radiation ered particles and the reference radiation: quality factor. It was shown [1] that the ion collection L∆ efficiency, f, of the ionization chamber with the local µ = ()L recombination, defined as the ratio of the ionization ∆ Cs current at a given polarizing voltage to the saturation with the cut-off ≈ 500 eV or ≈ 70 nm if the cut-off current, can be described by simplified formula: is expressed in units of length. Effective restricted LET 1 means here the mean value of restricted LET weighted f = 1− f by the transferred energy, taking into account the pri- 1+ µ ⋅ Cs mary particle and delta electrons with energy E > , f δ Cs which are considered as the separate particles associated where µ is the relative local ion density of the consid- with the primary ones. ered charged particles, defined in such a way that µ = 1 4. Ratio of unrestricted LET of the considered parti- for gamma radiation in a reference radiation field of cles and of the reference radiation: 137Cs under conditions of initial recombination, while ion collection efficiency in this field is fCs . The f and fCs µ = L / L0 for L ≥ L0 ≡ LCs = 3.5 keV/µ have to be determined at the same polarizing voltage. µ = 0.85 + 0.15 L / L0 for L < L0 Although the parameter µ has not clear physical 5. Ratio of the numbers of ion pairs generated in a meaning it is measurable quantity defined as: micro-site with the mass of about 1 fg crossed by a 1− f f particle track in the radiation fields of the consid- µ = ⋅ Cs − ered and reference radiations: f 1 fCs The parameter µ is constant for given radiation for µ = v the ionization chamber filled with pressurized gas at a vCs definite range of density. Therefore, it is considered as a physical parameter which characterizes the radiation 6. Ratio of the proximity function T(x) for the consid- quality. ered and reference radiations. In different theories of ionization energy deposi- T (x) µ = tion, the value of µ can be used as approximations of the T (x)Cs following quantities [2]: at x = 70 nm. 1. Ratio of the linear ionization density υ, of the con- The equations given above may yield somewhat sidered ionizing particles to the mean linear ioniza- different values of µ for the same, well defined radiation tion density of the standard gamma radiation υ : Cs but within inaccuracy range of about 10%, which is υ usually acceptable in radiation protection. In radiation µ = υ Cs fields of unknown composition, µ can be determined experimentally using a recombination chamber. The equation can be used at υ ≥ υCs ≈ 100 ion pairs/µm H2O.
References [1] N. Golnik, Raport IAE–20/A (1996) [2] M. Zielczyński et al., IAE Report B-10 (2007)
30 ANNUAL REPORT 2007 Radiation Protection and Dosiometry
RADIATION FIELDS OF GAMMA IRRADIATOR IN CALIBRATION ROOM OF RADIATION PROTECTION MEASUREMENTS LABORATORY K. Józefowicz, B. Boimski, P. Tulik, M. Zielczyński Institute of Atomic Energy In calibration hall of Radiation Protection Meas- To determine the gamma field of 241Am, emitting urements Laboratory (LPD) a new gamma irradiator [1] 60 keV gamma rays, two chambers of flat energy de- for calibration of dosimetric instruments has been in- pendence, Robotron VAJ with air chamber [4], and stalled within a PHARE program PL2002/000- ionization chamber KG-2, developed in IAE [5], have 632.07.01. The computer operated irradiator contains been applied. The air kerma rate determined with Ro- 137Cs, 60Co and 241Am sources, recommended by Inter- botron chamber at 1 m distance is (20 ± 1) µGy h-1 national Standard Organisation (ISO) for calibration of (Fig.2). To dependence the air kerma rate on the dis- dosimetric instruments [2]. The sources are stored inside tance from the source was determined with the KG-2 the heavy shield container and the pneumatic system is chamber. The full account of the results is given in [3]. used to transport a source into working position in a collimator. Computer program is applied to choose a 60.00 Sv/h] source and to establish the mode of irradiation. µ 50.00
40.00
30.00
20.00 Gy/h]and dose eq. rate [ µ
10.00
kerma kerma rate [ 0.00 0 0.5 1 1.5 2 2.5 3 distance, [m]
Fig. 2. The dependence of the air kerma rate (solid line) and ambient dose equivalent rate (dotted line) on the dis- tance from 241Am gamma source.
The accuracy of measurements performed with 241Am source is poorer than those with 137Cs and 60Co. The estimated total uncertainty of air kerma rate is 5.2%. The new gamma irradiator extends the possibility Fig. 1. Gamma irradiator. of the gamma calibrations to three energies; with higher dose rates available. The whole set of gamma field An extensive work has been performed to sources assembled in the calibration hall of Laboratory, determine the dosimetric parameters of the gamma provides an important tool for calibrations of radiation fields produced by irradiator [3]. Standard fields protection instruments and experiments with new de- of gamma radiation in LPD are traceable to Central vices. Office of Measures, Poland (GUM). The measurements of air kerma have been performed for sources of 137Cs and 60Co at several distances by the GUM officers, References [1] Source calibrator irradiator mod. IM6/M. Instruction using secondary standard ionisation chamber. Accord- and service handbook (Rev. 1.0 05/05). Tema Sinergie ing to the GUM certificates, the air kerma rate s.r.l. at distance 1 m on 31 December 2007 was equal [2] ISO-4037-3: 1999 to (29.39 ± 0.28) mGyh-1 for 137Cs and [3] K. Józefowicz et al., IAE Report B-14 (2007) (2.834 ± 0.028) mGyh-1 for 60Co. From the results of the [4] Röntgen-Gamma Dosimeter 27 040 – Technische Be- GUM measurements, the tables and graphs of air kerma schreibung und Bedienungsanleitung VEB Robotron- rate and ambient dose equivalent rate dependence on the Messelektronik “Otto Schön” Dresden (1987) [5] M. Zielczyński, N. Golnik, Monografie IEA 3 81 (2000) distance from the source were constructed. The esti- mated total uncertainty of the air kerma rate is 1% for 137Cs and 1 ÷ 2% (depending on the distance) for 60Co.
31
ANNUAL REPORT 2007 Nuclear Technology in Energy Generation
STAND AT THE MARIA RESEARCH REACTOR FOR THE STUDIES OF TRANSMUTATION OF FISSION PRODUCTS AND INCINERATION OF MINOR ACTINIDES S. Kilim1, E. Strugalska-Gola1, M. Szuta1, A. Wojciechowski1, Z.Woźnicki1, G. De Cargouet2 1Institute of Atomic Energy 2Nuclear Physics Institute AS CR PRI, Rez near Prague, Czech Republic Reduction of the radioactive wastes by transmuta- rods placed in the lead block and the second, thermal tion of radioactive long-lived fission products such as neutron zone consisting of metallic natural uranium rods 99Tc, 129I and 135Cs and by incineration of minor acti- (NH3) placed inside the polyethylene block. The natural nides is a very large field of study requiring significant uranium rods of 30 cm length, 2.72 cm diameter and experimental and financial support. 2.8735 kg weight are hermetically sealed in an alumin- ium cladding. We propose to replace the accelerator spallation source with the neutron source obtained by converting The sub-critical calculations for the stand at the the thermal neutrons from the horizontal channel of the horizontal channel of the MARIA research reactor have research reactor MARIA into fast neutrons. Taking into been performed using Monte Carlo N-Particle method- account the large flux of thermal neutrons in the hori- ology of version MCN PX. The calculations were nor- zontal channel, it is possible to use a fission converter malized to one external neutron source. The axial distri- i.e. an arrangement containing 235U placed in the axis of bution of total neutron flux in the experimental channels the horizontal beam. Thermal neutrons cause the fission of the lead support were calculated (Fig. 2). reactions producing fast neutrons needed. For the thermal neutron flux of 3 – 5·109 cm-2s-1 A natural metallic uranium blanket covering sev- at horizontal channel we obtained the total neutron flux eral fuel rods of EK-10 type constitutes the converter to in the first channel (d=15 cm) equal to ~5·10 6 cm-2 ⋅s-1 be placed on the moderator support (Fig. 1). The space and for the fifth (d=115 cm) ~103 cm-2 ⋅s-1. between the EK-10 type fuel rods will be filled with 1E-2 Neutron flux in channel lead which does not moderate the fission fast neutrons. at position (x,y)[cm] A polyethylene blanket covering the fuel rods has been (0, -15) (0, -50) also considered. 1E-3 (0, -65) (0, -95) (0, -115) 1E-4
1E-5 Total Total neutronflux[1/cm2]
1E-6
1E-7 -80 -40 0 40 z [cm] 80 Fig. 2. Axial distribution of total neutron flux in the experi- mental channels of the Pb support.
The system can be used to study the application of thorium fuel in the sub-critical assembly of the ADS.
Fig. 1. The simplified converter geometry of the stand. References [1] S. Kilim et al., IAE Report B-41 (2007) The converter (Fig. 1) consists of two zones: first the fast neutrons zone consisting of EK-10 type fuel
35 Nuclear Technology in Energy Generation ANNUAL REPORT 2007
RESULTS OF Y-89 IRRADIATION ON U/Pb-ASSEMBLY USING 1.6 GeV DEUTERON BEAM FROM THE JINR NUCLOTRON M. Bielewicz, S. Kilim, E. Strugalska-Gola, M. Szuta, A. Wojciechowski Institute of Atomic Energy 1.6 GeV deuteron beam The neutron field inside the U/Pb assembly of the 7,0E-05 Y88 S2 JINR Dubna experimental set-up ‘Energy plus Trans- mutation’ (EpT) was investigated with the Y-89 activa- 6,0E-05 Y87 S2 tion detectors. In the experiment the 1.6 GeV deuteron 5,0E-05 beam impinged on the cylindrical lead target surrounded Y86 S1 by uranium blanket shielded by polyethylene container 4,0E-05 [1,2]. The neutron field was determined with thirty five pure Yttrium 89 (99.9% Y-89) samples placed in speci- 3,0E-05 fied positions inside the U/Pb assembly. Neutron captu- 2,0E-05
re in Y-89 yields various (n,xnyp), reactions, where ‘x’ B[nuclei/g/deuteron] and ‘y’ are integer numbers. Isotopes created in these reactions are unstable and gamma active. After the 5.8 × 1,0E-05 13 10 beam deuterons were collected the gamma activity 0,0E+00 was measured with HPGe spectrometer. Taking into 0.0 11.8 24.0 36.2 48.4 account necessary corrections we have determined iso- Position along the target [cm] tope production per one gram of the sample and per one beam deuteron at specified positions inside the EpT Fig. 2. Axial distribution of isotopes produced at radial di- facility. The spatial distribution of the Y-88 isotope stance 3 cm from the 1.6 GeV deuteron beam axis by production was determined (Fig. 1). The presence of the spallation neutrons in Y89(n,xn) reactions. Y-87 and Y-86 was also revealed. The Y-88, Y-87, and Y86 production reactions are the threshold reactions with the threshold energy 11.5, 20.8, and 32.7 MeV, respectively. Hence, the isotope 1,8E-04 production ratio (e.g. Y87/Y88) depends on neutron 1.6 GeV 1,6E-04 energy spectrum and can serve as a spectral index. The deuteron 1,4E-04 region of constant spectral index (SI) was found in the beam 1,2E-04 middle of the EpT assembly (Fig. 3). 1,0E-04 8,0E-05 0,9 Y87/Y88 0.0 6,0E-05 3.0 0,8 R 6.0 4,0E-05 Y86/Y88 a d 8.5 B[nuclei/g/deuteron] iu 10.5 2,0E-05 0,7 s [ 13.5 c 0,0E+00 m 0.0 11.8 24.0 36.2 48.4 0,6 ]
Axial position [cm] 0,5
SI 0,4 Fig. 1. Spatial distribution of Y-88 produced by spallation neutrons in Y89(n, 2n) reaction. 0,3 0,2
The spatial distribution of the Y-88 isotope (Fig. 1) 0,1 is a superposition of two processes – beam deuteron 0,0 interaction with the samples and spallation neutron 0.0 11.8 24.0 36.2 48.4 interaction. During the deuteron interaction with yttrium Position along the target [cm] nuclei neutron stripping (d,dn) takes place in the central axis region. Beside the central region, at R ≥ 3 cm, the yttrium samples indicate only the spallation neutrons. Fig. 3. Axial distribution of the spectral index at radial dis- tance 3 cm from the 1.6 GeV deuteron beam axis. We found that isotope production attain a maximum of axial distribution in the second plane, 11.8 cm from the front of the EpT facility (Fig. 2). References [1] M. Krivopustov et al., JINR Preprint P1-2000-168, Dubna, (2000), Kerntechnik, 68, 48 (2003) [2] M. Krivopustov et al., JINR Preprint, E1-2007-7, Dubna (2007) [3] M. Bielewicz et al., IAE Report B-40 (2007) (in Polish)
36 ANNUAL REPORT 2007 Nuclear Technology in Energy Generation
UO2 GRAIN SUBDIVISION FOR VERY DEEP BURN-UP AND RELATIVELY LOW TEMPERATURE AND ITS IMPACT ON FISSION GAS RELEASE M. Szuta Institute of Atomic Energy
The beginning of the grain subdivision process in where S – total surface area, f - fission rate, r– aver- the nuclear fuel is observed at burn-up from ~60 age fission fragment range, V – volume of the subdi- MWd/kgU to 75 MWd/kgU [1] at the temperatures less vided fuel, g2 – constant. than 1200 oC. The peripheral region of the high burn-up When S r attains V then total surface area stops to UO2 fuel rod with a particular nano-structure is known as the “rim region”. The nano-structure changes start increase and the process of poligonization is accom- when the average burn-up exceeds ~40 MWd/kgU. The plished. marked decrease in the grain size is accompanied by an Assuming that r = 6 µm we obtain that total surface increase in porosity and a decrease in the signal for is equal to about 1.6 103 cm2/cm3. Relative density of fission xenon [2]. the fuel for this total surface area is equal to about 89 % It was established [1] that the local xenon concen- and the porosity is ~11 %. This value is comparable tration in the UO matrix attains a maximum as a func- with the experimental porosity data (15 %). Thus we 2 3 2 3 tion of the local burn-up. Coincident with the local obtain the total surface area of ~9 10 cm /cm for 85 % xenon concentration decrease is the local grain subdivi- relative density, which we call the limiting total surface sion in the rim area of the pellet. With increasing grain area (Sl). size, rim structure development rate is suppressed, and Our analysis let us postulate that the total surface the Xe depressions for the large-grained pellets are area of the fuel in the rim region depends on the burn-up about half of the value for the standard grain size pellet. b in simple way
Although the physical details of the process are not −cb S = S + (S − S )(1− e ) , (2) fully understood, an attempt has been made to describe bp l bp these processes by a simple model [3]. It is assumed that with Sbp – total surface area before the process, Sl – beside the modification of the properties of the “ather- limiting total surface area and c - a constant dependent mal” rim surface layer of the UO2 fuel pellet by neutron on the grain size. irradiation, the total surface area increases when the local xenon concentration decreases. Further on we From the solution of the defect trap model equa- tions for the high burn-up we obtain that the release rate assume that the fission gas release from the UO2 fuel during low temperature irradiation depends on the is equal to the birth rate knock-out process of the defect trap model and is pro- g f M = β f (3) portional to the total surface area. The knock-out proc- 2 tr i ess occurs also in the fuel transformed by grain subdivi- where Mtr is the concentration of gas atoms in the bub- sion. bles, and βi is formation yield of the intermediate gas of the i-th isotope. We assume that above a limiting value of fission fluency a more intensive process of irradiation induced In conclusion, the increase of gas concentration in chemical interaction occurs. Significant part of fission function of burn-up is explained by defect trap model gas products are chemically bound in the matrix of UO2. and the gas concentration at high burn-up (>120 It seems to be natural that the chemically bound fission GWd/tU) does not change. Nevertheless, the behavior gas atoms can form weak facets. At certain saturation of gas concentration in the intermediate burn-up range conditions subdivision of the grains can occur and the of 60 – 120 GWd/tU requires further study. increase in fission gas products release may be ex- pected. References In the defect trap model the fission gas release (R) [1] K. Lassmann, et.al., J. Nucl. Mater. 226 1 (1995) is described: [2] I.L.F. Rayet.al., J. Nucl. Mater. 245 115 (1997) [3] M. Szuta, IAE Report B-45 (2007) = R g2 f M tr Sr /V (1)
37 Nuclear Technology in Energy Generation ANNUAL REPORT 2007
ADVANCES IN THE SUB-CRITICAL MC CALCULATIONS FOR THE YALINA THERMAL FACILITY A. Wojciechowski, M. Szuta Institute of Atomic Energy
1E+5 YALINA-Thermal benchmark [1,2] is a part of the External neutron energy 2.5 MeV IAEA Coordinated Research Projects Analytical and 216 fuel rods
Experimental Analysis of Accelerator Driven Systems 1E+4 EC1 z = 25 cm and Low Enriched Uranium Fuel Utilization in Accel- EC1 z = 0 cm EC1 z = -20 cm
erator Driven Sub-Critical Assembly Systems. The Neutron [1/cm2*s] flux 1E+3 YALINA thermal facility is designed to study the ADS physics and to investigate the transmutation of MA and LLFP using an ADS. The main objective is to compare 1E+2 the results of different calculations, performed by dif- ferent research institutes, and experimental data. 1E+1 In this work we present preliminary results of cal- culation using MCNP4 [3] and MCNP5 [4] codes. The 1E+0 geometry is based on the specification of the YALINA- 1E-8 1E-7 1E-6 Thermal assembly [2]. time [s] Fig, 1. Total neutron flux (per one external neutron) time Yalina-Thermal assembly uses EK-10 type fuel dependence in the experimental channel EC1 at three rods and external neutron sources based on the fusion different position z = 0, +25 cm and -20 cm, 216 EK- reactions D-D (2.5MeV) and D-T (14MeV). Calcula- 10 elements and 2.5 MeV external source. tions [5] were performed for six different arrangements 0.96 of fuel rods and external neutron sources (Table 1).
Table 1. Experimental arrangements studied. Keff 0.94 Energy of external Number of EK-10 Mass of 235U [kg] neutron source fuel rods [MeV] 0.92 280 2.16 14.0 280 2.16 2.5 245 1.99 14.0 0.90 245 1.89 2.5 216 1.67 14.0 216 1.67 2.5 0.88
The time dependence of the spatial distribution of neutron flux and energy in the experimental channels 0.86 (EC1 – EC7) was calculated (Fig. 1). The effective 200 220 240 260 280 300 Number of fuel rods multiplication factor (keff) (Fig. 2), multiplication source factor (ks) and average prompt removal lifetime were Fig. 2.Calculation results of keff as a function of number of calculated. fuel rods.
References [1] S. Chigrinov et al., Nuclear facilities of the National Academy of Sciences of Belarus on the basis of highly enriched uranium. 7-12 Nov. 2004, IAEA,Vienna [2] V. Bournos et al., YALINA-Thermal Benchmark Speci- fications for the IAEA CRPs on Analytical and Experi- mental Benchmark Analysis on Accelerator Driven Sys- tems and Low Enriched Uranium Fuel Utilization in Accelerator Driven Sub-Critical Assembly Systems, March 2007 [3] J. F. Briesmeister, MCNP – A General MonteCarlo N- Particle Transport Code, La-12625-M Ver. 4b, 1997 [4] D. B. Pelopowitz, MCNPX – Users manual, LA-CP-05- 0369, ver. 2.5.0, April 2005 [5] A.Wojciechowski, M.Szuta, IAE Report B-42 (2007)
38 ANNUAL REPORT 2007 Nuclear Technology in Energy Generation
PRESENT STATUS OF IV-GENERATION LEAD-COOLED FAST REACTORS DEVELOPMENT M. Klisińska Institute of Atomic Energy International Committees GIF and INPRO have set circuit. The feasibility of primary coolant pump elimina- a number of technology goals for Generation IV nuclear tion has been confirmed. Most of LFR designs have no energy systems. They should provide sustainable energy separate steam generators. The working steam is gener- generation, promote long-term availability of systems, ated by direct contact of feed-water and liquid metal in effectively utilize the fuel, minimize the amount of reactor vessel and then is sent to the turbine. For the nuclear waste and reduce the long term fission products, steam Rankine cycle subcritical and supercritical op- be proliferation resistant, excellent in safety and reliabil- tions are considered. The presence of light fluid above ity, have a very low likelihood and degree of reactor the core drives natural circulation of the coolant. The core damage, eliminate the need for external emergency simplification of heat transport system allows remote actions, have an overall cost advantage over other en- deployment of lead-cooled systems. ergy sources and have a level of financial risk compara- The experience with lead-cooled reactors is rather ble to other energy sources. The Lead-cooled Fast Reac- scarce and requires research and development. The main tor (LFR) is one of the six IV-Generation nuclear sys- issue is the incompatibility of the coolant with the struc- tems selected by GIF and INPRO. tural and cladding materials. Cladding material must be The first in the world reactors using lead-bismuth also suitable for high-exposure of fast neutrons. Struc- eutectic – LBE (55 wt% Bi-45wt% Pb) as a primary tural material corrosion, coolant activation and chemis- coolant were Soviet propulsion reactors used in alpha- try, filtration of impurities are investigated in several class submarines (1972-1983). research centers all over the world. The major issue, associated with direct heat transfer from liquid metal to LFR, as fast reactor, turns 238U into feasible iso- water, is entrainment and carry over of primary coolant topes of plutonium so it can breed fuel. Fast Breeder vapour and Polonium (210Po is produced by 209Bi activa- Reactors can utilize uranium at least 60 times more tion) into the energy conversion system. Four fuel types efficiently than thermal spectrum reactor. are being considered: mixed-nitride (UN-PuN), metallic In contrast to sodium-cooled reactor the lead- and (U-Pu-Zr), oxide (UO2-PuO2) and carbide (UPuC). lead-bismuth eutectic-cooled reactors are safer due to Currently achieved core coolant outlet temperature the properties of the coolant. Lead and lead-bismuth is limited by material properties to 550–600°C, but in eutectic do not react vigorously with water or steam and the future it can be extended into the 750–800°C range, do not burn when exposed to air. This chemical inert- which is suitable for hydrogen production. In addition ness enables elimination of intermediate loop in the heat the Pb-alloy cooled reactors are capable of burning transport circuits with corresponding cost savings. Lead actinides and long-life fission products contained in the and lead alloys exhibit low neutron absorption and low spent fuel of LWRs. neutron slowing down power (this is important in fast reactors) and are also effective as neutron reflectors, Sizes of the lead-alloy-cooled reactors designs are which enables reduction of fuel enrichment. Heavy broad in scope: from small plants of 6 to 100 MWe – metal is an excellent gamma ray shield. Both coolants Angstrem (6 MWe), ENHS (50 MWe), LSPR (53 have relatively low melting temperature – 327°C for MWe), SSTAR (10÷100 MWe), SVBR-75 (75 MWe), lead and 123.5°C for LBE (98°C for sodium), extremely through medium – BREST-300 (300 MWe), to large – high boiling temperature at atmospheric pressure – BREST-1200 (1200MWe). 1750°C for lead and 1670°C for LBE – and high heat of References vaporization as well low vapour pressure at operating [1] M. Klisińska, Raport IAE-128/A, in Polish (2007) temperature. These properties enable using an ambient pressure primary system and high pressure cooling
39 Nuclear Technology in Energy Generation ANNUAL REPORT 2007
NUCLEAR POWER COMPONENT IN FORESIGHT ON ENERGY IN POLAND S. Chwaszczewski, J. Szczurek, P. Czerski, M. Łuszcz Institute of Atomic Energy The first technology foresight study on future de- The process was launched with STEEP and SWOT velopments in the energy sector in Poland was com- analysis aimed at isolating the main drivers of Polish pleted by the end of 2007 [1]. Looking ahead to 2030, future energy system. These analyses were useful to the study aimed to identify energy-related technologies, establish the preliminary list of possible variables re- scenarios, a mix of energy sources and infrastructure lated to future energy demand and supply as well as developments for Poland. One of the key requirements economical, political and social fields, which are likely was seen as a re-assessment of the future role of nuclear to have an important influence on the future develop- power in Poland to ensure security of power supply and ment of nuclear option. diversity, and avoid dominance by coal for reduction of The Road Maps with detailed time frame for each CO emissions. 2 implementation phase of the individual technology The paper [2] provides a short description of the within three scenarios have been developed (Fig. 2). methodology applied as well as main results and find- Similar to those R&D Road Maps have been designed ings of the foresight study referring to the perspective of with specification of the required actions. nuclear power option in Poland. The study can be broadly divided into two phases: Delphy survey with two rounds of expert judgment on anticipated techno- logical development and creation of Road Maps. A large majority of the Delphi survey participants expect the introduction of nuclear components in a mix of electricity sources in Poland just after 2020. How- ever, almost 17% of the respondents do not believe it will ever occur. Delphi respondents generally agree that the positive perception of nuclear fission in the public mind will be improved. Roughly half of the experts believe that at some point after 2030 high-temperature gas-cooled reactors will be in practical use for thermo-chemical processes. However, there are no chances for the commercializa- tion of this technology before 2030. The second important task of the project consisted in systematic creation of Road Maps for variant scenar- ios of nuclear power development in Poland up to 2030 (Fig. 1). Fig. 2. Road Maps on NPP technology implementation for individual scenarios.
The knowledge gathered gives insight into the pos- sible future constellations of nuclear power sector and on the actions necessary to increase the likelihood of the successful implementation nuclear technology in Po- land. The ultimate objective of the project was to pro- vide advice on energy R&D policy which should be useful for the decision makers. References [1] Technological Development Scenarios of the Fuel- Energy System for Assuring the Polish Energy Security, Part 1and 2, Central Mining Institute, Katowice (2007), in Polish Fig. 1. Research phases of the study to create Road Maps for [2] J. Szczurek et al., Nuclear Power Component in Fore- nu clear option development. sight on Energy in Poland, 15.1-15.8 in Proc. of Int. Conf. Nuclear Energy for New Europe 2007, Portorož /Slovenia/, September, 10-13, 2007
40 ANNUAL REPORT 2007 Nuclear Technology in Energy Generation
CORRELATION BETWEEN MULTIPLICITY, RAPIDITY AND IMPACT PARAMETER IN PION-XENON INTERACTIONS AT GeV ENERGIES B. Słowiński1,2, R. Sobczak2 1Institute of Atomic Energy 2Faculty of Physics, Warsaw University of Technology, Warsaw, Poland The impact parameter (IP) is the basic characteris- tic determining the initial geometry of the interaction of hadrons and nuclei with nuclei at intermediate and high energies. It enters in the appropriate theoretical forma- lism and, in particular, in the widely used Glauber mo- del. However, in experiments measured are only such quantities as multiplicity (M) of produced particles of definite sorts, their energies, momenta and emission angles. Using these observables constructed are such characteristics as various and numerous scaling varia- bles, longitudinal rapidity (LR), four-velocity transfer and centrality enabling categorization of experimental data. But the classification of this kind is by its nature of statistical meaning and always the question remains concerning the reliability and ambiguity of this procedu- re. In the present work we study the correlation be- tween the IP, M and LR of neutral and charged pions, protons and neutrons produced/emitted in the interac- tions of charged pions with xenon nuclei at momenta of 2.34, 3.5, 9 and 30 GeV/c. The correlation is investi- gated using JAM modeling code [1] whereas the above- listed reactions have been chosen because just in this case the corresponding experimental information is available, especially on neutral pions, registered within Fig. 1. Average multiplicity of neutral pions vs. impact para- 4π geometry and practically without limitation on their meter (left) and average rapidity vs. impact parameter energy [2], except to the case of the reaction at (right) calculated using the JAM code [1] for the reac- 30 GeV/c which is selected to follow the energy behav- tion of charged pions with xenon nuclei at four incident momenta: 2.34, 3.5, 9 and 30 GeV/c. ior of the investigated correlation only. Simple analytic parameterizations of investigated correlations have been References obtained, too. As an example of our results we present [1] Y. Nara et al., Phys.Rev. C61, 024901 (2000) here the dependence on IP of the average multiplicity [2] L.S. Okhrimenko et al., JINR Rapid Communications. and average rapidity of neutral pions produced in the 2(22)-87, 12 reaction of πXe at 3.5 GeV/c calculated with the JAM code (Fig. 1).
41 Nuclear Technology in Energy Generation ANNUAL REPORT 2007
PARAMETRIZATION OF FLUCTUATION OF ENERGY LOSS IN ELECTROMAGNETIC CASCADES AT INTERMEDIATE ENERGIES B. Słowiński1,2, P. Duda1, W. Dzikowski1 1Faculty of Physics, Warsaw University of Technology, Warsaw, Poland 2Institute of Atomic Energy Our present knowledge on the fluctuation of energy loss in electromagnetic cascades (EC) induced by gamma quanta of high enough energy in dense amorphous materials comes to integral characteristics of the phenomenon [1,2]. But it is the major contributor of uncertainties of energy and direction of gammas regis- tered in electromagnetic detectors (for example, [1]). The influence of this fluctuation is meaningful espe- cially in the range of intermediate energies, i.e. from about 100 MeV to several GeV when in EC participate not so much produced particles.
In the work we continued to study longitudinal fluctuation of energy losses (LEL) in EC created in liquid xenon by gamma quanta of energy Eγ= 200, 550, 2375 and 3375 MeV at four different cut-off energies Ec.o. = 0.6, 1.25, 2.0 and 3.0 MeV, and two values of threshold A= 0.5 and 0.7. The investigation was done using the EGS modeling code [3]. Modeled are in total 48000 events of cascades. The obtained distributions of Eγ and Ec.o. dependence of the fluctuation defined as r.m.s. of LEL have been satisfactorily parametrized by the generalized gamma function: =α ⋅ β − δ γ P(tA) tA exp( tA / ). (1) Our results show that all parameters attain their as- Fig. 1. Distributions on gamma quanta energy Eγ of the pa- ymptotic regimes at Eγ ~ 600 MeV. The behavior is γ γ rameter for two threshold values A at which the part demonstrated in the parameter distributions vs Eγ for A=0.5 and A=0.7 of EC energy is released on aver- various Ec.o (Fig. 1). The calculations were performed age. The cascades are initiated in liquid xenon by for two values, 0.5 and 0.7, of the threshold A, i.e. the gamma quanta of energy Eγ at the cut-off energy Ec.o. = part A at the EC depths at which released is, on the 0.6, 1.25, 2.0 and 3.0 MeV. average, 0.5 and 0.7 of the total EC energy loss, corre- spondingly. Analogous distributions have been obtained References for β and δ parameters. The conclusion is that near the [1] B. Słowiński, Phys.Part.Nucl. 25, March-April 1994, 600 MeV the description of LEL fluctuation in the form 173, Radiat.Phys.Chem. 49 327 (1997) (1) turns out to be universal. [2] C. Grupen, Particle detectors. Cambridge University Press. (1996) [3] W.R. Nelson et al., The EGS4 Code System. SLAC-265 (1985)
42 ANNUAL REPORT 2007 Nuclear Technology in Energy Generation
SEARCH FOR THE UNIVERSAL PARAMETERIZATION OF ELECTROMAGNETIC PROFILES IN HEAVY AMORPHOUS MEDIA B. Słowiński1, P. Duda1, M. Sikorski2 1Institute of Atomic Energy 2Faculty of Physics, Warsaw University of Technology, Warsaw, Poland It is commonly agreed that the average longitudinal medium, should be calculated as the best fit to the rele- profile of electromagnetic cascades (EMC) initiated by vant experimental results [1]. high energy gamma quanta in uniform amorphous me- In the work the simulation of EMC developing in dia may be satisfactorily parameterized by a gamma- the six most frequently used materials: Bi Ge O type function: 4 3 12 (BGO), CdWO4 (CWO), liquid Xe, W, PbWO4 (PWO) = ⋅ bt ⋅ − and Si has been performed for three values of primary f t (t) at t exp( t / ct ), energy Eγ: 500, 1500 and 3000 MeV (i.e., covering the where the parameters at, bt and ct are to be determined characteristic transition region) and two values of Ec.o.: by fitting to experimental data for some materials being 0.6 and 1.25 MeV (i.e., as typical for most experi- of interest (e.g. [1]). Among these parameters mainly ct ments). For each set of parameters (i.e. material, Eγ and depends both on the cut-off energy Ec.o. of cascade par- Ec.o.) 5000 histories were traced using the EGS code [2] ticles and material characteristics. Somewhat more and all parameters determining both longitudinal and ambiguous is the description of radial EMC profiles but radial EMC profiles have been estimated. The depend- from the viewpoint of simplicity one can admit that the ence of the slope parameter ct on the medium character- relevant distribution is of the form of the weighted sum istics ρZ/A, where ρ is the medium density, Z and A are of two exponents its electric charge and atomic number (or corresponding f (r) = a ⋅ exp(−r / b ) + c ⋅ exp(−r / d ) average values for compounds) have been determined r r r r r (Fig.1). Moreover, it has been found, that the above where the parameters ar, br, cr and dr containing infor- mentioned parameterization functions correspond with mation about the initial and cut-off energies, and on a our modeled data reasonably well.
Fig.1. The example of the slope parameter values estimated from simulations of EMC for different incident gamma quantum energy and different materials.
References [1] B. Słowiński, Phys.Part.Nucl., 25(2) 173 (1994) [2] W.R. Nelson et al. The EGS4 Code System. SLAC-265 (1985)
43 Nuclear Technology in Energy Generation ANNUAL REPORT 2007
ANALYSIS OF PROSPECTS OF WIND ENERGY IN POLAND A. Strupczewski Institute of Atomic Energy In view of the large subsidies to wind power and Capital costs for wind power are very high. plans of its fast development there is a new discussion A comparison of an NPP with the load factor of 0.88, on whether it is necessary do develop nuclear power, if which is less than the actual average value in the world, the renewable energy sources can be made available. and wind power plants with load factors of 0.,34 on land The example of Denmark is quoted as the case of and 0.45 offshore [3] – which is very high for wind a country which is very successful in developing wind turbines - shows that the capital costs per unit of energy power. On the other hand, Both European Parliament generated over the lifetime are much higher for wind and governments of such countries as France and UK than for nuclear power plants [1]. see the necessity of nuclear power as a stable and cheap source of energy. The review of facts concerning wind power is therefore needed. The changeability of wind is proverbial. An exam- ple of daily changes of electricity demand and of wind output in a chosen week in summer 2002 in Denmark shows that there are days when the wind system simply does NOT produce any energy.
Fig. 2. Unit investment per unit of electricity produced over the lifetime is higher for wind than for nuclear power [1].
In Poland the average annual wind velocity in the best locations is within the range of 4 to 5 m/s., which is much less than 7÷11 m/s considered as good conditions for wind power.
Fig. 1. Loss of wind power in Denmark in a week in August 2002 [1].
The changes can occur very rapidly. When there is no wind, it is necessary to have reserve power plants ready to step in and take up the load. This means that for each wind power plant we must build another of nearly the same power, which will be just waiting idle until the wind. This is a heavy investment load. Moreover, the nominal power of a wind turbine is misleading – in Fig. 3. Wind velocity in Poland at the seaside (blue line) and practice the wind power is much less than the maximum in south regions (dashed red line) [1]. rated value, so e.g. in Germany the average annual load factors for wind turbines range from 16 to 20%. Moreover, the power of the hydropower is small in Poland which makes problems of compensation of wind Fast changes of wind power can not be compensa- changes very difficult. Thus although wind power is ted by coal fired power plants. Gas can partly help, but renewable, and so should be used in Poland, related the real answer lies in hydropower, which can be easily costs will be high. regulated. Denmark is fortunately situated close to the large hydropower system of Scandinavia, which pro- duces 178 TWh/a and can accommodate both sudden References increases and decreases of wind power. But Denmark [1] A. Strupczewski, Biuletyn PSE, 4-5 4 (2007) [2] H. Sharman, Civil Eng. 158 66 (2005) has to pay for it – it must send most of its energy abroad [3] J. Eliasz, A. Biwan , Energetyka 2006, Wrocław Uni- at dumping price, and so loses annually one billion versity of Technology, 8 – 10 November (2006) Danish crowns [2]. 44 ANNUAL REPORT 2007 Nuclear Technology in Energy Generation
FACTORS IMPLYING THE IMPLEMENTATION OF NUCLEAR POWER IN POLAND A. Strupczewski1, K. Jaworska2, A. Patrycy2, G. Saniewski2 1Institute of Atomic Energy 2BSiPE Energoprojekt, Warszawa In Poland above 94% of electricity is produced which it will be necessary to build much deeper coal from coal fired power plants. In the European Union the mines and produce coal at much higher costs. dominating electricity source is nuclear power, which in Polish economy develops and is expected to conti- 2004 provi8ded about 32% of overall needs. Coal nue this trend so that in 2025 the electricity needed in provided 29.7% of electricity needed in the EU, and gas Poland will be 220 TWh. An analysis of existing and 18% [1]. potential energy sources has shown, that without nuclear Nuclear power offers Poland advantages in three power the energy needs cannot be satisfied. respects: Coal production is slowly decreasing year after - Security of supply, important in view of the limita- year. Gas contribution should not be assumed, because tions of possibilities of use of coal. in near future the availability o gas will go down, and its - Economical profits, as nuclear power is presently goes up. Thus, if we assume that in 2025 coal and gas the lowest cost stable energy Skurce. will keep their present production quotas (143 TWh/a), - Health and environmental protection, as nuclear it will be an optimistic view. power means clean air, water and soil around the Renewable energy sources in Poland are quite limi- NPPs. ted and much more expensive than coal or nuclear po-
CO2 emission permits introduced by the European wer. The potential of hydroenergy is presently about Commission which add to the price of coal about 22 4 TWh/a, and till 2025 further 3 TWH can be devel- euro/ton CO2, and even more the emission permits oped, biomass can provide up to 6 TWh, biogas (from which limit Polish emissions much below actual use, are all resources) up to 14 TWH and wind 8 TWh. very strong incentives to stop building coal fired power Together this yields 174 TWh. We are short by plants. Nuclear power is economically competitive even 46 TWh – and this is the equivalent of 2 NPPs with without consideration of emission permits [1]. Nuclear 2 units of 1600 MWe power each. industry has made great progress on the road of reduc- tion of capital costs and improvement of operational Besides being necessary and cheap, nuclear power parameters and is presently the lowest cost energy sour- is also clean The technical studies in the EU [2] and in ce (Fig. 1). Poland [1] are in full agreement: the question for Poland is not whether to build NPPs or not, but rather how soon The operational resources of organic energy source it is technically possible. in Poland will be exhausted within some 40 years after
200,0
Capital
150,0 Depreciation Maintenance Sorbents 100,0 Ash storage
unit [PLN/MWh]costs Liquid waste Water 50,0 Emissions Taxes Fuel 0,0 NPP Gas Coal Lignite
Fig. 1 Electricity generating costs in Poland according to the study of Energoprojekt Warsaw [1].
References [1] A. Strupczewski et al., Biuletyn PSE, 4-5 4 (2007) [2] http://www.iea.org/textbase/npsum/ElecCostSUM.pdf 45 Nuclear Technology in Energy Generation ANNUAL REPORT 2007
46
ANNUAL REPORT 2007 Condensed Matter Physics
REGIONAL LABORATORY OF NEUTRONOGRAPHY J. J. Milczarek, J. Jankowska-Kisielińska, A. Czachor Institute of Atomic Energy The Regional Laboratory of Neutronography trons ( λ = 0.15 nm) monochromatized and analyzed (RLN) provides experimental facilities and research with the (111) Bragg reflection from Si single crys- experience in the field of thermal neutron scattering tals. The full-width at half maximum of the instru- studies of condensed matter and materials engineering. mental distribution is in the region of 30"- 40". The The laboratory operates six horizontal channels of the angular distribution of transmitted neutrons may be MARIA reactor and six instruments designed for elastic measured in steps of 0.125". The instrument is de- and inelastic neutron scattering (Fig. 1). A beam time signed for studies of the average size of magnetic allocation at our facility can be applied for by submit- domains, large precipitations or other micro-objects ting proposals directly to the responsible researchers that cause neutron scattering. mentioned below or to Prof. A. Czachor. Proposals are Dr J. J. Milczarek tel. +48 22 7180233 evaluated by the Project Selection Board of the RLN e-mail: [email protected] which consists of the representatives of institutes and 4 H5 – enhanced resolution diffractometer equipped universities interested in doing research using neutron with Cu (200) double-crystal monochromator; angular scattering at the RLN. The Board's Chairman is Prof. resolution ~4’; neutron wavelength range: 0.06 – L. Dobrzyński of the Sołtan Institute for Nuclear Stud- 0.1 nm; scattering angle range: 0º - 110°. It may be ies, Świerk. used as the polarized neutron spectrometer. Polarized neutron beam is then produced by two subsequent Bragg reflection, first from the (200) plane of the Cu monochromator and then - from magnetized Co-Fe single crystal. 7 H8 Dr J. J. Milczarek tel. +48 22 7180233
e-mail: [email protected] M
. H7
5 H6 - triple-axis spectrometer. The instrument is de-
A S C signed for studies of the crystal and magnetic lattice H3 dynamics by inelastic neutron scattering. The instru- 6 o H6 M. ment is equipped with PG (FWHM = 0.4 ) mono- chromator, analyzer and filter set; neutron flux den- H5 H4 5 M S M M. -2 -1 S . sity at the sample position is 5.1·10 cm s for
A S C λ C A = 0.235 nm. The range of scattering angles:
A S 10º - 110º. C 5 A 1 Dr J. Jankowska-Kisielińska. tel. +48 22 7180137 C 2 C e-mail: [email protected] 6 H7 - triple-axis spectrometer, designed for the inelas-
tic neutron scattering studies. PG monochromator, Fig. 1. Floor plan of the neutron spectrometers of RLN in the analyzer and filter set is installed. Zn monochromator Maria reactor hall. (FWHM = 15') and analyzer set is also available with neutron flux density at the sample position Available instruments at horizontal channels (H 3-7) 5.5·105 cm-2 s-1 for λ = 0.152 nm. The range of scat- and responsible researchers. tering angles: 10º - 110º. H3-a small angle neutron diffractometer designed for 1 Dr J. Jankowska-Kisielińska. tel. +48 22 7180137 studies of inhomogeneities like precipitations e-mail: [email protected] and micropores in materials ( λ = 0.237 nm, Qmin≈ 0.1 nm-1). Each instrument is computer controlled. The labo- Dr J. J. Milczarek tel. +48 22 7180233 ratory uses an unified computer code for all instruments. e-mail: [email protected] The program offers the window system with text and 2 H3-b double axis diffractometer, used to study crys- graphics modes, zooming option for data extraction and talline or magnetic structures. Zn, PG, Cu(200) and visualization of measurement results. Available sample Si(311) monochromators are available. The range of environment includes helium microcooler (8 K – scattering angles: 0º - 90º. The energy analysis of the 300 K), liquid nitrogen cryostats, vacuum furnaces and scattered neutrons is also possible. magnets. The sample environment parameters can be Dr J. J. Milczarek tel. +48 22 7180233 registered in real time during measurements. The neu- e-mail: [email protected] tron and gamma radiography facility installed at the H8 horizontal channel is described in the next section. 3 H4 – small-angle double-crystal neutron diffractome- ter. The instrument operates with monoenergetic neu- 49 Condensed Matter Physics ANNUAL REPORT 2007
NEUTRON AND GAMMA RADIOGRAPHY STATION AT THE NUCLEAR RESEARCH REACTOR MARIA A. Czachor, J. J. Milczarek Institute of Atomic Energy Weak interaction of neutrons with typical metals, tion beam and converter screen. The sample support can such as Fe, Cu and Al, combined with a strong scatter- hold objects with mass to 100 kg. ing of the neutrons by hydrogen, allows them to pene- trate macroscopic metallic objects and to reveal the internal distribution of hydrogen containing compo- nents, such as petrol, water, organic materials and cor- 1 m roded parts. The strong beam of gamma radiation, emit- H8
s r ted from nuclear reactor, also can be used to provide an o t a m i l l extra information on the interior of the object investi- o c gated. Having passed the investigated object, the neu- tron or gamma radiation reaches the fluorescent screen neutron (converter), where it is converted into visible light beam (Fig. 1). The two-dimensional projection of the object H7 object on the screen is registered with the CCD camera and optical processed using computer methods. system
CONVERTER NEUTRONS beam trap
MIRROR
LIGHT OBJECT
water
asphalt
paraffin or computer neutronstop ZOOM LENSES system
ACQUISITION SYSTEM CCD CAMERA Fig. 2. General layout of the neutron and gamma radiography station at the research reactor MARIA.
Fig. 1. The main parts of the neutron radiography station. The parameters of the station are: 100 < L/D < 200, Cd ratio 20, and the neutron flux density 1.1·107 cm-2 s-1 The neutron and gamma radiography (NGR) sta- at the sample position for L/D=150. The spatial resolu- tion at Świerk is situated at the horizontal beam H8 of tion is of the order of 0.1 mm. The high quality images the MARIA reactor (Fig. 2). The station has started its are produced with the exposition time of 1.6 s, but satis- operation in July 2001. The following investigations factory quality of the full resolution radiograms is have been performed in 2007: obtained for the exposition time of 0.6 s. - Temperature and gravitation dependence of water migration in beds of granular materials. Good uniformity of the white field was confirmed - Nondestructive testing of technical objects. and the linear resolution of 0.1 mm for the optical mag- - Observations of drying of wet kaolin samples. nification used in most experiments was established. The result of the resolution test is presented in Fig. 3 Due to the ample space by the channel H8 of the containing the radiogram (Fig. 3a) of three 2 mm thick reactor MARIA and its relatively large neutron flux, this slabs made of cadmium, lead and Plexiglas with holes NGR facility has many advantages, especially for diag- of 2 mm diameter. The edges of the holes are separated nostics of industrial objects. Remote-control support by gaps with widths decreasing from 1 to 0.1 mm up- devices and modern analogue and digital registration wards. The optical density plot (Fig. 3b) reveals distinct equipment will allow us to scan and record the internal cusp on the left corresponding to the smallest separation structure of large objects like engines, refrigerators, as gap (0.1 mm). well as some elements of their internal dynamics. The station is equipped with the mobile sample support- carrier, enabling the remote control tuning of the posi- tion of the investigated object with respect to the radia-
50 ANNUAL REPORT 2007 Condensed Matter Physics
Attempts were made to observe processes induced by various external factors. One of the most interesting processes observed was the evaporation of water from the wetted sample of aerated concrete when heated by the electric current. The sequence of images from this process is presented in Fig. 5. The process was observed during approximately 60 s after switching the voltage supply on. The sample was covered with three layers of acrylic paint and wetted for 24 h with 10% NaCl water solution. The sample was 35 mm long with the cross section 10 mm × 10 mm and the ac voltage of 70 V was applied through the gold electrodes. The water evapora- a tion through the damaged paint cover was very rapid leaving the dry region (visible in the radiograms as the 1.2 blue tilted strip) in the middle of the sample. ) s t i
n 1
u The merits of NR are inaccessible within standard
y r X-ray or optical methods, supporting the expectations of a
r 0.8 t i interest in NR from many researchers of industrial, b r a
( agriculture, medical and other roots. 0.6 y t i s n
e 0.4 d
l a c i t 0.2 p O 0 20 30 40 50 distance (mm) b Fig. 3. The artificially colored radiogram of three sheets of (from the left) cadmium, lead and Plexiglas with 2 mm diameter holes separated by gaps of width from 0.9 to 0.1 mm (a), (b) – the plot of optical density distribution (a) t = 5 s along the line across the holes’ centres in the cadmium sheet.
Radiograms of objects with separated regions con- taining ordinary and heavy water demonstrate the strong incoherent scattering of neutrons by hydrogen nuclei. The strong effective absorption of neutrons by ordinary water produces dark regions in the images. As an exam- ple the radiogram of the aluminium double container with ordinary and heavy water is presented in Fig. 4. The thickness of both liquid layers was 1.3 mm. (b) t = 10 s
(c) t =55 s
Fig. 5. The process of the water evaporation induced by heat- ing of the wet porous sample with the electric current. Fig. 4. The radiogram of flat double container filled with The time is counted from the switching the voltage sup- ordinary water (left part) and heavy water (right side) ply on. of 1.3 mm thickness.
51 Condensed Matter Physics ANNUAL REPORT 2007
MATERIAL RESEARCH LABORATORY OF THE IEA W. Szteke Institute of Atomic Energy The Material Research Laboratory (MRL) of the - cutting out samples from the irradiated reactor Institute of Atomic Energy is engaged in research cover- components, ing all aspects of materials engineering and in techno- - sample preparation for metallographic and X-ray logical processes developed in the powder metallurgy, examinations, welding, brazing and soldering domains. The investiga- - thinning of metal samples for transmission electron tions are carried out on both structural materials and microscopy, their welded joints, including the examinations of irra- - optical microscopy and microhardness measure- diated materials. The Laboratory is equipped with mod- ments, ern devices for the scientific and applied studies of - swelling control of materials and density materials. All work in MRL is performed according to determination, the Quality Assurance Program. - thermal treatment and annealing, - stereo macroscopic examination and stereo photog- The MRL incorporates the Hot Laboratory which raphy, was put into operation in February 1993 after the au- - chemical analysis. thorization by the National Inspectorate for Radiation At the end of 1998 the laboratory for non- and Nuclear Safety. The facility was designed to pro- destructive testing of materials was put into operation in vide maximum flexibility for a wide research program the MRL. The applied test methods include: involving metallurgical, physical, and chemical testing - visual inspection, of irradiated structural materials of nuclear reactors. The - liquid penetration inspection, main part of the laboratory is a set of 12 hot cells with - ultrasonic examination, lead shielding suitable for handling of radioactive mate- - radiographic inspection, including X-ray and iso- rials up to 4 TBq related to 60Co. Every cell is equipped tope radiography, with up-to-date sophisticated devices for examination of - structure investigation using replicas method. radioactive materials. The main equipment includes: Since 1999 the MRL has been the exclusive repre- - Instron 8500 Dynamic Testing System with two sentative of the SAQ Kontroll AB Sweden in Poland for 100 kN frames for testing of tensile and compres- using and promoting in Poland the special diagnostic sive strengths, low cycle fatigue resistance, fracture programme SACC 4.0 (Safety Assessment of Compo- toughness, bend characteristics and crack growth nents with Cracks). resistance at -150˚C to 1000˚C temperature range. The experience of the Material Research Labora- - Instrumented Wolpert Pendulum Impact Testing tory in radioactive materials analysis was employed in Machine PW 30/15 for dynamic tests of Charpy-V Materials Testing Centre formed within the consortium type specimens carried out at -150˚C to 800˚C tem- of the IEA and the Radioactive Waste Management perature range, for determination of significant Plant for quick identification and categorization of ra- force and deflection values, partial energy values, dioactive or nuclear items of unidentified or unknown characteristic fracture mechanical values. origin. The Materials Test Centre is a part of Polish - DIA-TESTOR 7521 Wolpert Hardness Testing system for response to illicit trafficking and inadvertent Machine for tests using Brinell, Vickers and Rock- movement of radioactive materials. The main equip- well procedures. ment of the MTC consists of: - DRD-4 X-ray Diffractometer for structure analysis, - ISOCS Shield System for in situ gamma spectros- copy with a germanium detector. - ROBOFIL 200 Spark Erosion Machine for speci- - InSpector 1000 – portable NaI gamma spectrometer mens preparation. with neutron probe. The devices are fully automated, remotely op- - Radiagem 2000 – portable dose rate meter with two erated and instrumented, equipped with computer con- intelligent probes SABG 15 and SAB 100 for alfa, trol systems for machine control, data acquisition and beta and gamma radiation. analysis of results. MRL IAE holds the Accreditation Certificate of The remaining equipment of the hot cells complex Testing Laboratory No AB 025 which confirms fulfill- provides an opportunity to perform: ment of the ISO/IEC 17025:2001 criteria and the Tech- nical Requirements of Technical Inspection DT-L/95.
52 ANNUAL REPORT 2007 Condensed Matter Physics
NUCLEAR POTENTIAL WELLS AND BOUND ENERGY STATES AS EVALUATED FROM EXPERIMENTAL DATA ON NEUTRON SCATTERING LENGTHS A. Czachor1, P. Pęczkowski1,2 1Institute of Atomic Energy 2Institute of Experimental Physics, Warsaw University, Warsaw, Poland Using the neutron scattering lengths b determined b tgx 1− = (2) experimentally for a majority of isotopes in last decades RA x [1], one can extract systematic information on some nuclear properties. The intriguing „scatter” of the ex- where perimental values of b, showing no systematic depend- = h−1 − ence on the mass number A or charge number Z needs x 2mVZA RA (3) interpretation. In this work, on extending the use of The construction of Eq. (2) allows three possibili- known formulas of the theory of neutron scattering on ties for the left hand side, corresponding to three essen- nucleus represented by a rectangular radial symmetry tially different potential wells (Fig.1). potential well (or barrier), we have determined the depths V0 of the potential well and for many isotopes the It has appeared, that for the deep potentials the po- position of the bound state energy level EB in the well. tential depths have to be assigned to four domains dif- fering by the solution label n1. It is the assignment to 4 different s-type solutions of the Schrödinger equation for the rectangular radial potential well. Attributing a given isotope to the n1-label is a non-continuous process vs. A. It partially explains the observed scatter of the b- values vs. A (Fig.2). Within the same model the bound-state energy lev- els in the deep potential wells have also been deter- mined [3].
-20
-25 0 15 30 45 60 75 90 105 120 135 150 165 180 195 210 225 240 255 -30 -35 -40 Fig. 1. Graphical representation of three possible types of -45
rectangular radial-symmetry potential wells (barriers) 0 - Colors show three domains of solutions of Eq. (2), V -50 depending on the ratio of neutron scattering length b to -55 the “classic” nucleon radius R). Yellow - shallow well, -60 V0 < 0, b < 0; violet - potential barrier, V0 > 0, 0 < b -65 < R; green - deep well, V0 < 0, b > R, -70 -75
-80 We have chosen the simplest model of the radial A rectangular potential well of the depth V , and the radius 0 Fig. 2. Potential well depths for deep wells. They were as- signed to 4 domains of possible solutions of Eq. (2): The R = r A 3/1 (1) A o S ≠ 0 isotopes are included as dark green points. with r0 = 1.3 fm. References On assuming the „attractive” rectangular potential [1] Neutron Data Booklet, Ed. Dianoux A. J., Lander G., well of the radius R = R and the depth V < 0 , one A ZA ILL – Neutrons for Science, (2001) [2] T. Mayer-Kuckuk, Kernphysik, Teubner B. G., arrives under the usual boundary conditions at the equa- Stuttgard, (1979) tion relating the potential depth and scattering length [3] A. Czachor, P. Pęczkowski, IAE Report B-59 (2007)
53 Condensed Matter Physics ANNUAL REPORT 2007
GROWTH DEFECTS AND LATTICE DEFORMATION IN Ca0.5Sr0.5NdAlO4 SINGLE CRYSTAL K. Wieteska1, W. Wierzchowski2 , A. Malinowska2,3, M. Lefeld-Sosnowska4, W. Graeff5 1Institute of Atomic Energy 2Institute of Electronic Material Technology, Warsaw, Poland 3Faculty of Physics, Warsaw University of Technology, Warsaw, Poland 4Institute of Experimental Physics University of Warsaw, Warsaw, Poland 5HASYLAB at DESY, Hamburg, Germany
Oxide materials of general composition ABCO4 which may indicate the deformation of the lattice (where A = Ca, Sr, Ba, B = La, Nd, Pr and C = Al, Ga) (marked by D in Fig. 2. with the tetragonal perovskite-related K2NiF4-type structure are considered as promising substrate materials for high temperature superconducting (HTSc) thin films, elements of thermal radiation receivers and other electronic devices due to their electrochemical and Fig. 2. Synchrotron radiation white beam transmission section thermal properties and a good lattice matching. Crystals topograph of Ca0.5Sr0.5NdAlO4 single crystal, -36-7 re- flection, λ = 0.047 nm. of high structural quality are required for such applica- tions hence the characterization of crystal lattice defects The synchrotron back reflection monochromatic is of a great importance. The crystals of solid solution in topographs revealed long-range lattice deformation of A A’ BCO or ABC C’ O systems provide a possi- x 1-x 4 x 1-x 4 the sample (Fig. 3). bility of obtaining the adjustable lattice parameter by appropriate selection of the A/A’ or C/C’ ratio [1-6]. Apart from striations the white beam back reflec- tion topographs revealed a significant concentration of The Ca Sr NdAlO single crystal grown by the 0.5 0.5 4 individual defects in form of precipitates and disloca- Czochralski method in the [100] direction was chosen tions. The nature of the observed defects is under inves- for studies. The investigations were performed using tigation. synchrotron radiation, white and monochromatic beam, topography. The white beam synchrotron experiments included projection and section topography in reflection and transmission geometry. The samples were studied by taking monochromatic beam topographs in the 0.111 nm radiation. The main defects revealed with all topog- raphic methods were segregation fringes associated with non homogenous crystal composition. Fig. 3. Synchrotron radiation monochromatic beam back reflection topograph taken at low-angle rocking curve The synchrotron back reflection topographs ex- flank, 400 reflection, λ = 0.111 nm. posed through the mesh revealed the local lattice misori- entation associated with a lattice parameter change. The References local lattice misorientation manifests itself in bending of [1] M. Berkowski et al., Appl. Phys. Lett. 57 632 (1990) shadows of the wires (Fig. 1). [2] A. Pajaczkowska, A. Gloubokov, Progress in Crystal Growth and Characterisation 36 123 (1998) [3] A. Novoselov et al., Cryst. Res. Technol. 40 405 (2005) [4] A. Novoselov et al., Mater. Res. Bull. 36 1789 (2001) [5] A. Novoselov et al., J. Cryst. Growth 287 305 (2006) [6] A. Malinowska et al., submitted to J. Cyst. Growth.
Fig. 1. Synchrotron radiation white beam back reflection projection topograph taken through the fine mesh with 0.7 mm wire spacing, Ca0.5Sr0.5NdAlO4 single crystal: - 374 reflection, λ=0.044 nm.
The white beam section topographs revealed also the shape of the segregation fringes corresponding to the successive position of the growth surface. We may notice characteristic kinks of the section topographs
54 ANNUAL REPORT 2007 Condensed Matter Physics
SYNCHROTRON TOPOGRAPHIC INVESTIGATION OF BULK GaAs1–xPx AND GaAs1–x Px:Te CRYSTALS K. Wieteska1, W. Wierzchowski2, J. Gronkowski3, G. Kowalski3, T. Słupiński2, W. Graeff4,2 1Institute of Atomic Energy 2Institute of Electronic Materials Technology, Warsaw, Poland 3Institute of Experimental Physics, University of Warsaw, Warsaw, Poland 4HASYLAB at DESY, Hamburg, Germany The efforts to grow good ternary and quarternary It was found that that the topographs of the doped AIIIBV single crystals are stimulated by the demand for sample of GaAs1–xPx:Te (Fig. 1) exhibits a complicated substrates with well-defined lattice parameters and en- contrast connected with instabilities of the growth front. ergy gap. It is, however, a difficult task due to segrega- In some regions a more distinct lattice deformation as tion phenomena occurring in multicomponent liquid well as some extended contrasts are observed. They solutions of AIIIBV compounds [1]. Therefore, only thin may be connected with inclusions of not perfectly crys- layers are easily grown using epitaxial techniques on the tallised material. On the other hand, the topographs of relevant binary substrates. In the reported case the undoped crystal (Fig. 2) exhibited a much better perfec- GaAs1-xPx and GaAs1–xPx:Te (x ≤ 0.2) ingots were tion, with much more regular growth bands. However, grown at a significantly reduced growth velocity (~1 some growth instabilities are still visible in the left part mm/h) in order to control supersaturation in the melt. of the picture. Previous results of characterisation by means of high- resolution X-ray diffractometry and conventional dif- fraction topography were published elsewhere [2]. The conventional topographs revealed large segregation effects. The present investigations of the same samples, cut both perpendicular and parallel to the growth axis, were performed using synchrotron white-beam topography. The best results were obtained using back reflection projection and transmission section methods. In both cases it was possible to obtain relatively clear images of Fig. 2. Back reflection projection topograph of GaAs1–xPx segregation fringes and other lattice defec. It should be sample. noted that transmission section topographs provided an image of segregation fringes along the intersection of The transmission section topograph of the undoped the narrow incident beam with the sample. crystal provides a distinct image of the growth bands inside the sample in the plane of intersection of the narrow beam perpendicular to the surface with the sam- ple (Fig. 3).
Fig. 3: Transmission section topograph of GaAs1–xPx sample.
References Fig. 1. Back reflection projection topograph of GaAs1–x Px:Te [1] H. J. Sell, J. Cryst. Growth 107, 625 (1991) sample. [2] G. Kowalski et al., phys. stat. sol. (a) 204, 2578 (2007)
55 Condensed Matter Physics ANNUAL REPORT 2007
CRYSTALLOGRAPHIC DEFECTS AND FACETING IN Er-DOPED Yb3AL5O12 CRYSTALS K. Kołodziejak1, W. Wierzchowski1, K. Wieteska2, M. Malinowski1, W. Graeff3, T. Łukasiewicz1 1Institute of Electronic Materials Technology, Warsaw, Poland 2Institute of Atomic Energy 3HASYLAB at DESY, Hamburg, Germany
The Yb3Al5O12: Er crystals are a perspective laser material providing efficient emission in the near infra- red range [1]. The trivalent erbium ion provides the 2.94 µm line very useful for medical applications and the 1.55 µm line for light guide communication (also for eye-safe lasers for military applications).
The Yb3Al5O12 (YbAG) Czochralski grown crys- tals (undoped and doped with erbium) were studied using synchrotron X-ray monochromatic beam topogra- phy, recording of the rocking curves and white beam topographic methods. The crystallographic identifica- tions of the facets was performed together with direct evaluation of growth front radius from the transmission section topographs. The investigation proved the possi- a b bility of growing Yb3Al5O12 crystal of good structural Fig. 2. White beam projection back reflection topographs of quality with high concentration of erbium dopant. The Er doped Yb3Al5O12 crystals revealing segregation most important observed defects were segregation fringes and sets of facets: a – with 10% erbium, fringes and growth facets. The monochromatic beam b – 1.5% erbium. topographs confirmed slight changes of lattice parame- ter induced by the segregation of the erbium and low The observed facets were identified as correspond- level of strains in the crystals (Fig. 1, 2). ing to {221}, {211}, {311} and {301} planes. The first type form a core, observed in most of crystals, some- times neighbouring to {211} and {311} ones. The third type of facets corresponds to the planes inclined at 43º and occurs for mostly convex growth surface. The iden- tification of the facets was confirmed by the transmis- Fig. 1. Monochromatic beam back reflection topograph in sion section topographs, which show the location of symmetrical 444 reflection of Yb3Al5O12 crystal with growth bands in the intersection of the sample with the 1.5% of erbium in 0.111 nm radiation exhibiting segre- incident synchrotron beam, and enabled us to determine gation fringes and some rosettes corresponding to the the curvature of the growth surface (Fig. 3). dislocation outcrops.
a
b
Fig. 3. Transmission white beam section topographs of Yb3Al5O12 crystals doped with a – with 30%, and b - 1.5 % erbium re- vealing the striation fringes corresponding to the successive location of growth surfaces in the plane intersected by the narrow incident beam perpendicular to the sample. The thickness of both samples is of 550 µm, while the horizontal di- ameter of the reproduced area is of 7.5 mm. The radius of the growth surface is 4 cm and 2 cm, for (a) and (b) case, re- spectively.
References [1] D. Pacheco, B. Di Bartolo, J. Lumin. 14, 19 (1976)
56 ANNUAL REPORT 2007 Condensed Matter Physics
TOPOGRAPHIC STUDIES OF GROWTH DEFECTS IN YVO4 CRYSTALS K. Wieteska1, W. Wierzchowski2, E. Wierzbicka2,3, A. Malinowska2,4, M. Lefeld-Sosnowska3, T. Łukasiewicz2, W. Graeff5 1Institute of Atomic Energy 2Institute of Electronic Materials Technology, Warsaw, Poland 3Institute of Experimental Physics, University of Warsaw, Warsaw, Poland 4Faculty of Physics, Warsaw University of Technology, Warsaw, Poland 5HASYLAB at DESY, Hamburg, Germany
Yttrium orthovanadate crystals (YVO4) are pre- dicted for replacing formerly used YAG garnets as a laser material due to higher quantum efficiency and lower excitation level. It is especially useful in micro laser systems excited with semiconductor laser diodes. No topographic studies of YVO4 crystals were de- scribed till now in the literature. Some recent results concerning growth of YVO4 are described in [1-3]. YVO4 is of zirconium tetragonal structure with the D4h space group and lattice parameters a = b = 0.712 nm and c = 0.629 nm. Fig. 2. Complex subgrain boundary structure revealed by white beam topograph in the sample cut out from an- A number of samples cut out from Czochralski other part of the crystal. grown YVO4 crystals were studied with X-ray topog- raphic methods using both synchrotron and conven- tional X-ray sources. The synchrotron studies were done with both monochromatic and white X-ray beam in back reflection geometry.
The topographs revealed a relatively high density (104 cm-2) of weak point-like contrasts which can be interpreted as dislocation outcrops. In some regions of a the crystal close to its boundary the glide bands were observed (Fig. 1).
b
Fig. 1. White beam topograph of YVO3 revealing dislocation outcrops glide bands (located mainly in right side) and subgrain boundary on the left. It was also found that in some regions the disloca- c tion forms a local subgrain boundaries. A complicated Fig. 3 a - c. Monochromatic plane wave topographs: (400) structure of subgrain boundaries may be seen in Fig. 2. reflection,λ = 0.115nm, direction of the beam projec- The topographs did not reveal any segregation fringes tion along the normal to (001) planes. The pictures proving high homogeneity of chemical composition. were taken for three angular positions passing the ma- ximum of the rocking curve. The misorientation of the lattice connected with these boundaries was studied in some synchrotron References monochromatic beam experiments in multicrystal ar- [1] S. Wu et al., J. Cryst. Growth 249 176A (2003) rangement (Fig. 3). The experiment allowed us to find [2] H. Zhang et al., J. Cryst. Growth 283 438 (2005) the misorientations less than few minutes of arc. [3] Y. Yu etal., Materials Letters 60 1014 (2006), J. Cryst. Growth 249 176 (2003)
57 Condensed Matter Physics ANNUAL REPORT 2007
SYNCHROTRON DIFFRACTION STUDIES OF MONO- AND MULTICRYSTALLINE SILICON DOPED BY NEUTRON TRANSMUTATION IN MARIA REACTOR K. Wieteska1, W. Wierzchowski2, C. Pochrybniak1, J. J. Milczarek1, W. Graeff3 1Institute of Atomic Energy 2Institute of Electronic Materials Technology, Warsaw, Poland 3HASYLAB at DESY, Hamburg, Germany The interest in multicrystalline silicon comes from tion between the defect structure and the irradia- the possibility of replacing the crystalline silicon by tion/annealing processes. We hope that further studies cheaper material in some applications like photovoltaic help to identify some observed changes in the subgrain technology. The main concern is the homogeneity of structure as produced by this treatment. impurity distribution, which may precipitate at grain boundaries. The possible solution to this problem may be with application of the homogeneous doping by neutron transmutation. A series of undoped and slightly doped multicrys- talline silicon wafers were irradiated in research reactor MARIA with thermal neutrons of flux density 1014 cm- 2s-1 with exposure times of 100 and 42 hours. After appropriate annealing the resistivity of the irradiated wafers decreased from the initial value of 500 – 800 to 0.7 Ωcm and 2 Ωcm for longer and shorter exposure times, respectively. The radiation defects and their evo- lution in the subsequent processes of thermal annealing were separately studied with positron annihilation method indicating the presence of vacancy clusters and V-P complexes. In present studies the white beam synchrotron ra- diation was used for examination of the multicrystalline silicon wafers. The back reflection patterns provided a b information on the grain sizes and their angular distribu- Fig. 2. White beam topographs (enlarged images) of selected tion (Fig. 1). In many cases the method revealed many grains revealing subgrain structure and glide bands. details of the defect structure of particular silicon grains (Fig. 2). The examination of the monocrystalline samples proved that the defect structure introduced by NTD and annealing processes does not produce strains disturbing the diffraction pattern (Fig. 3).
a b Fig. 3. The interference fringes in Bragg-case section topog- raph caused by sample curvature proving the coher- Fig. 1. Synchrotron white beam projection back reflection ence of defect clusters in annealed NTD sample. patterns taken at glancing angle of 5º, a – reference sample and b 100 h NTD annealed sample. The interesting phenomenon was the decrease of The observed defects included some subgrain the diffraction peak width for higher irradiation dose structure connected with glide bands as well as some and higher annealing temperature. distinct black contrasts which may be attributed to some inclusions. It was not possible to find a direct connec- 58 ANNUAL REPORT 2007 Condensed Matter Physics
ANISOTROPY OF THE NEUTRON SCATTERING ON THE Mn0.71Ni0.29 ALLOY J. Jankowska-Kisielińska, I. Fijał-Kirejczyk, K. Mikke Institute of Atomic Energy, Świerk, Poland The subject of the present work was to test the spa- The SW neutron-scattering was measured for the tial anisotropy of the critical neutron scattering in the both parallel and perpendicular directions for energy up paramagnetic phase and the anisotropy of spin-waves in to 18 meV (Fig. 2). The SW velocity is higher for the the antiferromagnetic phase of the Mn0.71Ni0.29 alloy. direction parallel to the anisotropy axis than for the perpendicular direction, but the difference is close to the The earlier study of the critical scattering in the accuracy limits: v = 19±1 meV nm and v⊥ = 16±1 FCC Mn Ni demonstrated the pronounced uniaxial || 0.62 0.38 meV nm obtained from data for 18 meV for 15K. The anisotropy both in the static and dynamical part of the SW damping was found similar for the two directions. generalized susceptibility [1]. The anisotropy axis is parallel to the scattering-vector reduced to the paramag- 400 netic Brillouin zone. The spin-wave velocities for this (X,1,0) alloy were 21 and 15 meV nm for the spin wave vector 300 parallel and perpendicular to the anisotropy axis [2]. It should be stressed that any significant anisotropy of the 200 SW scattering was found neither in FCC Mn-Fe alloys 100 y t nor in Mn-Ni alloys with the tetragonal structure i s
n 0 e
(Mn0.843Ni0.137, inter-metallic compound MnNi). It was t
n 400 I also not mentioned for FCC Mn0.73Ni0.27 [3]. The ques- (0,1+X,0) tion, what is the reason of the strong anisotropy ob- 300 served in Mn0.62Ni0.38 alloy, is still open. The present extension of our study on the Mn-Ni alloys aims to find 200 the concentration dependence of the anisotropy. 100
Our main result for the paramagnetic phase of the 0 Mn0.71Ni0.29 alloy is that the correlation length is bigger -0.2 -0.1 0 0.1 0.2 for the direction parallel to the anisotropy axis than for X the perpendicular one (Fig. 1). The ratio obtained at Fig. 2. The intensity distribution of the neutron scattered on 35K and 45K above TN is κ⊥/κ|| = 1.5±0.2, where κ⊥ and spin waves with energy 18 meV measured at 15K for [100]-upper part and [010] direction in the vicinity of κ|| are the reciprocal correlation lengths for perpendicu- lar and parallel directions. The same ratio obtained the (010) reciprocal lattice point. The dashed lines rep- ± resent the shape of the scattering cross-section and the earlier for the Mn0.62Ni0.38 was 2 0.2 for temperature solid lines –the folding of the cross-section with the range 5-100K above TN. resolution function.
In conclusion, we found the anisotropy of the cor- 200 relation range in the paramagnetic phase and of the (0,1+X,0) 160 (X,1,0) observed spin wave velocity in the AF phase in the Mn0.71Ni0.29 alloy. The effect it is less pronounced than y t
i 120
s similar anisotropy found in the Mn0.62Ni0.38 alloy. Our n e
t result indicates that magnetic interactions in Mn-Ni
n 80 I alloys are less extended for higher Ni concentration. 40
0 References [1] J.J. Milczarek, et.al., J. de Physique 49 C8 183 (1988) -0.3 -0.2 -0.1 0 0.1 0.2 0.3 [2] K. Mikke, J. Jankowska-Kisielińska, B. Hennion, Ap- X plied Physics A 74 Suppl., S616-S618 (2002) Fig. 1. The intensity distribution of the paramagnetic neutron [3] B. Hennion, M. T. Hutchings, R. P. Lowde, M. W. scattered with energy 5.5 meV measured at 453K for Stringfellow, D. Tocchetti, Proc. 2-nd Gatlinburg Conf. [100] direction (open symbols) and [010] direction on Neutron Scattering, (R. M. Moon, editor) 825 (1976) (filled symbols) in the vicinity of the (010) reciprocal lattice point. The solid lines represent the folding of the cross-section with the resolution function.
59 Condensed Matter Physics ANNUAL REPORT 2007
EFFECT OF GRAVITATION ON WATER MIGRATION IN GRANULAR MEDIA J.J. Milczarek, I. Fijał-Kirejczyk, J. śołądek , M. Chojnowski, G. Kowalczyk, Z. Jurkowski, J. śołądek Institute of Atomic Energy Our previous studies indicate that the rate of water The experiments were carried out with the dynami- imbibition of beds of coarse granular media such as cal neutron radiography with spatial resolution of sand or gravel depends on the direction of the water 0.2 mm, with frames recorded every 2 s. The effect of front migration against gravity [1,2]. The aim of this the gravity on the water front motion was discernible work was to study the effect of gravity on the kinetics of even for beds composed of fine grains (Fig. 1). water migration in unsaturated (dry) simple granular The experimental results were analysed in terms of systems composed of chemically uniform grains of the Washburn-Bosanquet (W-B) theory of water migra- selected size. tion in porous medium. Assuming the correctness of the The present studies [3,4] were performed on quartz W-B description for the initial stages of the imbibition sand and corundum beds of different grain size the effective capillary radius was estimated from the (Table 1). The beds were in the form of ~130 mm long imbibition rate parameter a (Table 1). However, our and ~7 mm diameter cylinders and were placed verti- analysis reveal that the theory is not valid for overall cally at stabilized temperature. It was possible to supply time behaviour of wetting front motion (Fig. 2) [3, 4]. lower or upper end of the sample with water inducing Our results suggest that the main reason for this serious the migration opposite or according to the gravity, re- discrepancy is that the theoretical approach underesti- spectively. mates the energy dissipation in the migration of liquid in the porous medium neglecting the roughness of pore surface boundary. fine quartz ° Table 1. Effective porosity, imbibition rate parameter and 100 50 C effective capillary radius of the bed. imbibition effective grain size rate parameter capillary material [mm] at 30°C radius ra -1/2 d[mm] [mm s ] [ m] fine quartz 0.09 – 0.16 8 1.45 coarse quartz 1.0 – 1.2 5.4 0.65 10 corundum ~0.05 4.8 0.52
1 10 100 t [s] ↓ 100 ↑ theory 100 corundum r = 0.1 mm fine quartz 50°C 30°C d[mm]
10 theory d [mm]d r = 1.5 µm 10 1 10 100 t [s] Fig. 2. Comparison of the W-B theory predictions and experi- 1 10 100 mental results for the time dependence of the imbibition t [s] front position in fine quartz bed. Fig. 1. Dependence of the position of water front on time in fine quartz and corundum beds at 50ºC. The vertical References arrows, ↓ and ↑, indicate the direction of the wetting [1] J.J. Milczarek et al., IAE Report B-31 (2004) front motion, according and opposite to the gravity, re- [2] J.J. Milczarek et al., IAE Report B-45 (2006) spectively. [3] J.J. Milczarek et al., IAE Report B-36 (2007) [4] J.J. Milczarek et al., Acta Phys. Pol. A 113 1245 (2008)
60 ANNUAL REPORT 2007 Condensed Matter Physics
NEUTRON RADIOGRAPHY STUDIES OF DRYING KAOLIN SAMPLES J.J. Milczarek1, I. Fijał-Kirejczyk1, J. śołądek1, J. Banaszak2, Z. Jurkowski1, J. śołądek1 1Institute of Atomic Energy 2Institute of Technology and Chemical Engineering, Poznań University of Technology, Poznań, Poland
Experimental studies on drying processes of wet where R denotes the cylinder radius, xo is position of solid bodies are of importance for technology and theo- the cylinder axis on the horizontal Ox line, and ℜ is retical model construction [1-3]. The aim of our work the operation of extracting of the real component. [4] was to apply the dynamic neutron radiography in observations of drying of kaolin cylinders. The significant differences in the spatial depend- ence of the Σ calculated for different times of drying The present studies [3] were performed on the 30% eff wet kaolin cylinder (25.4 mm high, 27.3 mm diameter). were found (Fig. 2). The sample was observed for 72 hours during convec- tive drying at temperature of ~18°C. 0.15 0 h 3 h
0.1
eff 20 h Σ 72 h
0.05
t = 0 t = 20 h t = 72 h 0 Fig. 1. Neutron radiography images of drying kaolin cylinder. 36 40 44 48 52 56 60 64 The time elapsed from the beginning of the process is position [mm] given below of each image. Fig. 2. Neutron macroscopic cros- section along the central horizontal line of drying kaolin cylinder. The experiments were carried out with the dynami- cal neutron radiography with spatial resolution of 0.2 Our results reveal the decreasing water content in- mm. The brightness of the sample images registered side the drying kaolin cylinder. It seems that initially the during the process increased with time (Fig. 1). water is distributed less uniformly than in the later stages of the drying process. However, the strong scat- The experimental results were analyzed in terms of tering component makes the determination of the water the usually assumed exponential dependence of the content distribution difficult. The estimation of the neutron beam intensity I on the composition and thick- spatial distribution of water should be based on simula- ness L of the sample: tions taking into account both neutron absorption and = −ΣL scattering in the sample. I Io e References where the macroscopic neutron cross section Σ de- [1] Porous media: Theory and Experiments, R. de Boer pends substantially on the chemical composition of the (Ed.) Kluwer, Dordrecht (1999) material [5]. [2] S.J. Kowalski in Porous Media, W. Ehlers, J. Blum (Eds), Springer, Berlin (2002) In order to discuss the changes in the water content [3] G. Musielak, J. Banaszak, Transp. Porous Med. 66 121 of the sample the effective macroscopic neutron cross (2007) Σ [4] J.J. Milczarek, et al. IAE Report B-58 (2007) section eff was calculated from the local optical den- [5] Practical Neutron Radiography, J.C. Domanus (Ed.), sity D in the specific point of the sample image Kluwer, Dordrecht (1992) = D ∑eff ℜ 2 − − 2 2 ( R (x xo ) )
61 Condensed Matter Physics ANNUAL REPORT 2007
NEUTRON SCATTERING STUDIES OF WO3:ZrO2 NANOCOMPOSITES J.J. Milczarek, E. Iller, J. śołądek, I. Fijał-Kirejczyk, Z. Jurkowski, J. śołądek Institute of Atomic Energy The atomic ordering and the nano-scale structure of The elongation of the inhomogeneities was found also the WO3 : ZrO2 composites produced by sol-gel tech- for 1:1 and 3:2 composites. However, the space correla- nique [1, 2] and annealed at 500, 650 and 800°C was tion of their positions is much weaker than that for 1:2 studied by wide and small angle neutron diffraction [3]. composites even after 500°C annealing. The atomic ordering of the composites was studied -1 1:2 in the wide range (10 – 80 nm ) of the scattering vector 500°C 5h Q . It was found that the diffractograms for samples 12 annealed at 500°C do not reveal any Bragg peaks but only a broad halo centered near Q of 40 nm-1 (Fig. 1a). 8 For samples annealed at 650ºC four distinct maxima P(r) were observed for each composition. The diffracto- 4 grams of 800ºC annealed samples consist of many Bragg peaks (Fig. 1b) characteristic for fully fledged crystalline structure. 0
100 0 10 20 30 40 50 a r [nm] 1:1 500°C 5h wzr_03 80 30
60 1:2 800°C 2h 40 20 Intensity [counts]
20 P(r) 10 0
0 20 40 60 80 a Q [nm-1] 0
wzr_05 1:1 800°C 5h 0 20 40 60 1200 b r [nm]
800 Fig. 2. The plots of distance correlation function P(r) for 3: 2 WO3 : ZrO2 nanocomposite after the 500°C and 800°C annealing.
Intensity[counts] 400
Our results [3] confirm that the WO3 : ZrO2 com- posites easily crystallize and the rate of process in- 0 20 40 60 80 creases with the temperature. We found that in the com- b Q [nm-1] posites annealed at 500°C the inhomogeneities of aver-
Fig. 1. Neutron diffraction pattern for 1:1 WO3 : ZrO2 nano- age diameter of 50 nm and highly warped boundary composite after two different thermal treatments. surface exist. For higher annealing temperatures the cylinder-like particles are formed. The nano-scale structure of the composites was de- termined by the small angle neutron scattering in References [1] M.S. Dadachov et al., Appl. Radiation and Isotope 57 0.1 nm-1 < Q < 1 nm-1 region. The analysis of the SANS 641 (2002) data was performed with the GIFT program of the PCG [2] A. Deptuła et al., Polish Patent No. 172618 (1997) package [4] in order to obtain the distance correlation [3] J.J. Milczarek et al., IAE Report B-38 (2007) function P(r) and the structure factor S(Q). [4] J. Brunner-Popela, O. Glatter, J. Appl. Cryst. 30 431 (1997) The GIFT results indicate that the inhomogeneities found in 1:2 samples are spheres of radius 23 nm after 500°C annealing but their shape evolves with increasing annealing temperature into 60 nm long cylinders of 12 nm radius found after annealing at 800°C (Fig. 2).
62 ANNUAL REPORT 2007 Condensed Matter Physics
MÖSSBAUER EFFECT STUDIES OF Dy(Fe0.7-xNixCo0.6)2 A. Stoch1, P. Guzdek2, P. Stoch3, J. Pszczoła2, J. Suwalski3, P. Zachariasz3, T. Wójcik3 1Institute of Electron Technology, Kraków, Poland 2Faculty of Physics and Applied Computer Science, AGH, Kraków, Poland 3Institute of Atomic Energy The heavy rare earth (R) - transition metal (M) ferri- tice, is analogous for that for other intermetallic series magnets RM2, including substituted ferrimagnets, have [5]. been widely studied for both their fundamental interest The average values of the hyperfine interaction pa- and practical applications [1,2]. The ferrimagnetism of rameters at 4.2K, estimated from the fitting procedure the RM compounds results from the coexistence of 2 i.e., the isomer shift IS (with respect to pure iron metal, 4f(5d) and 3d magnetism [3]. The present work aim was at 300K), the magnetic hyperfine field µ H and the the effect of the substitution of Fe with Ni in the 0 hf quadrupole interaction parameter QS have been deter- Dy(Fe Co ) compound (Fe/Ni substitution introduces 0.7 0.3 2 mined for seven equidistant x values (Fig. 2). additional 3d electrons). The studies were performed using Mössbauer effect technique and the hyperfine interaction parameters were determined in the Dy(Fe0.7- xNix Co0.3)2 series.
The Dy(Fe0.7-xNix Co0.3)2 (x = 0.0-0.7) alloys have cubic, Fd3m, MgCu2-type (C15) crystal structure [4]. The measurements were performed at 4.2K on polycrys- talline samples using a standard transmission technique with a source of 57Co in Rh. The collected 57Fe Möss- bauer spectra present complicated pattern (Fig. 1).
Fig. 2. Hyperfine interaction parameters of the Dy(Fe0.7-xNix Co0.3)2.
The isomer shift decreases with x and experimental points can be described by linear equation: IS(x)= (-0.028x+0.042) mm/s (Fig. 2.1). The magnetic hyper-
fine field µ0Hhf equals 24.93(17) T for Dy(Fe0.7Co0.3)2 and decreases with increasing Ni content x. The experi-
mental points tally well with the formula: µ0Hhf(x)= (-10.75x2-6.71x+25.07) T (Fig. 2.2). The quadrupole interaction parameter increases slightly with x and were fitted with the formula: QS(x)=(0.010x+0.045) mm/s 57 Fig. 1. Fe Mössbauer effect spectra of the Dy(Fe0.7-xNix (Fig. 2.3) Co0.3)2 intermetallics (4.2K). References The spectra are composed of a number of subspec- [1] A.M. Tishin, Y.I. Spichkin, The Magnetocaloric tra and this complexity arises from the different nearest Effect and its Applications, Institute of Physics, neighborhoods of the observed Fe-atoms resulting from Bristol (2003) Fe/Ni substitution. Each Fe, Ni, Co nearest neighbor [2] K. Yano et al., J. Phys.: Condens. Matter 18 6891 surrounding introduces its own subspectrum and thus its (2006) [3] I.A. Campbell, J.Phys.F: Metal Phys. 2 L47 (1972) own set of hyperfine interaction parameters. The prob- [4] A. Jabłońska et al., J. Alloys Compd. (in press) lems in determining the number of nearest neighbour [5] P. Stoch et al., J. Alloys Compd. 375 24 (2004) surroundings, the number of subspectra, the probabili- ties of the particular subspectra and the fitting procedure of the spectra in the case of three elements, with ran- domly distributed atoms, in the transition metal sublat-
63 Condensed Matter Physics ANNUAL REPORT 2007
BAND STRUCTURE CALCULATION OF DY(Fe0.7-X NiXCo0.6)2 INTERMETALLICS A. Stoch1, P. Guzdek2, P. Stoch3, J. Pszczoła2, J. Suwalski3, P. Zachariasz3, T. Wójcik3 1Institute of Electron Technology, Kraków, Poland 2Faculty of Physics and Applied Computer Science, AGH, Kraków, Poland 3Institute of Atomic Energy The heavy rare earth (R) - transition metal (M) The magnetic moments per Fe, Co and Ni atom and the ferrimagnets RM2, including substituted ferrimagnets, stoichiometrically weighted moments per transition have been widely studied for both their fundamental metal atom calculated for the Dy(Fe0.7-xNixCo0.3)2 series interest and their practical applications [1,2]. The ferri- decrease with increasing number of 3d electrons per magnetism of the RM2 compounds results from the atom (Fig. 2). interplay of 4f(5d) and 3d electrons [3].
The electronic band structures of Dy(Fe0.7-xNix Co0.3)2 intermetallics were calculated by an ab-initio self-consistent Full - Potential Linearized Augmented Plane Waves (FLAPW) method implemented in the WIEN2K code [4]. The generalized gradient approximation (GGA) in the parametrization of Perdew - Burke - Ernzerhof [5] was employed. The GGA+U method was used for 4f electrons including the on site correlation energy U= 7eV to settle down the energy scale of Dy 4f electronic states [6]. A supercell approach was applied with the supercell equivalent to eight crystal unit cells. The numbers of Fe, Co and Ni atoms inside the supercell matched the value of the stoichiometry parametr x. The calculations were carried Fig. 2. The calculated magnetic moment mM of transition out for randomly positioned Fe, Co and Ni atoms on the metals vs. average number n of 3d electrons for the sites of the transition metal sublattice. Dy(Fe0.7-xNixCo0.3)2 series (1 - M=Fe, 2 - M=Co, 3 - M=Ni, 4 - weighted magnetic moment per transition The average stoichiometrically weighted density of metal atom). 3d states (DOS), per transition metal, and the densities of 3d states, for Fe, Co and Ni, were calculated. An The conclusion is that the substitution of Fe atoms example of the results is presented for the with Ni ones reduces the magnetic moments per Fe, Co Dy(Fe0.7Co0.3)2 and Dy(Fe0.2Ni0.5Co0.3)2 compounds and Ni atom. In effect the average magnetic moment per (Fig. 1). transition metal atom is reduced very strongly with increasing average number n of 3d electrons in the in- termetallic compound.
References [1] A.M. Tishin, Y.I. Spichkin, The Magnetocaloric Effect and its Applications, Institute of Physics Publishing, Bristol (2003) [2] K. Yano et al., J. Phys.: Condens. Matter 18 6891 (2006) [3] I.A. Campbell, J.Phys.F: Metal Phys. 2 L47 (1972) [4] P. Blacha et al., Wien2k, An Augmented Plane Wave + Local Orbitals Program for Calculating Crystal Proper- ties, Techn. Universität Wien (2001) [5] J. P. Perdew et al., Phys. Rev. Lett. 77 3865 (1996) [6] W.A. Harrison, Elementary Electronic Structure, World Scientific, Singapore (1999)
Fig. 1. Weighted (M) and individual (Fe, Co and Ni) densities of 3d electrons states (DOS) as functions of energy E.
64 ANNUAL REPORT 2007 Condensed Matter Physics
STRUCTURE AND PROPERTIES OF 137Cs CONTAINING WASTE GLASS P. Stoch, J. Suwalski, P. Zachariasz, T. Wójcik Institute of Atomic Energy High level radioactive wastes (HLW) from both the connected with the cation modifier Na+ occurs at 458.8 -1 nuclear power industry and military nuclear pro- cm . Introduction of Cs2O causes the shift of the main grammes are currently immobilised by vitrification. band to 1017cm-1 and the glass modifiers band to Borosilicate glass provides the very suitable medium for 455.9 cm-1. It means that the presence of Cs+ increases the majority of the species present in these wastes [1, 2]. the degree of polymerization of the network. Introduc- It prevents leaching of radio nuclides by water- immobi- tion of Ca causes the appearance besides of the Si-O-Si lisation effect. Environment protection legislation and band (1021 cm-1) the band at 946 cm-1, which is charac- increase of disposal costs makes the vitrification of the teristic for silicate and aluminate glasses, containing low level nuclear waste (LLW) favorable [3]. The calcium. This indicates the formation in the network the treatment of such waste begins with reduction of their domains containing Ca; also yielding the shift of the -1 volume by incineration. The ash containing radio iso- [BO3] band to 1422 cm . The band connected with the topes, is suitable for vitrification and ceramization by cation modifiers becomes shifted to 471 cm-1. This incorporating it into the composition of boro- means that the presence of 5% mass of Cs2O, affects aluminosilicate glass, similar to that used in nuclear significantly the glass structure. The effect is stronger power industry. when Cs2O and CaO are introduced simultaneously; then the degree of polymerization of the silicate network Our studies concerned the influence of Cs as a increases producing the observed shift of the Si-O-Si characteristic component of ash after combustion of band toward higher frequencies (from 1000 LLW on the structure and properties of borosilicate to 1021 cm-1). glass. The effect of introducing Cs2O or both Cs2O and CaO on the properties of boro-aluminosilicate glasses is Introduction of Cs into the basic glass Na2O – B2O3 little known, as the compounds are not used in tradi- – Al2O3 – SiO2 (waste glass) in order to immobilize its tional glass manufacturing. radioactive isotope induces changes in the structure and in the properties of the glass. This results from consid- Four different compositions of glass were studied. erable crystallochemical differences between Cs+ and (Table 1). CaO was present in glasses 1 and 2, and Na+ as the glass structure modifiers. In the presence of was added as the characteristic component of ash ob- even a relatively small amount of Cs O the degree of tained from paper incineration. The other ash compo- 2 polymerization of the glass network as well as its stabil- nents: SiO , Al O were already present in the base 2 2 3 ity increases. Evidently this means the increase of the glass (glass 3) composition. In two glasses a part of chemical durability of the glass. On the other hand Na2O (5 mass %) was replaced by Cs2O (glass 2 and 4). above glass transformation temperature (Tg), cesium Table 1. The chemical compositions of investigated Glassem. acts as the strong depolymeriser, increasing the ten- Chemical dency for crystallization of the basic glass. It becomes compositions Glass 1 Glass 2 Glass 3 Glass 4 incorporated into the structure of the newly formed [mass %] crystal phases such as the chemically resistant alumi- SiO2 48.5 48.5 56 56 nosilicates. Similar changes are induced by the introduc- B O 7.5 7.5 15 15 2 3 tion of CaO into the glass. Our results confirm and ex- Al2O3 8 8 8 8 CaO 18 18 - - plain the suitability of borosilicate glass for inactivation Na2O 18 13 21 16 of the incinerated hospital and laboratory wastes con- 137 Cs2O - 5 - 5 taminated with radioactive Cs [4].
Our results have shown that the introduction of References [1] W. Donald, Glass Technology: Eur. J. Glass Sci. Tech- relatively small amount of Cs2O (5 % mass) instead of Na O induces considerable changes in the structure and nol. A 48 155 (2007) 2 [2] M.I. Ojovan, W.E. Lee, An Introduction to Nuclear the thermochemical properties of boroaluminosilicate Waste Immobilisation, Elsevier Science,Amsterdam, Na2O – B2O3 – Al2O3 – SiO2 glass. FTIR spectrum of (2005) Na2O – B2O3 – Al2O3 – SiO2 glass is characterized by [3] I. A. Sobolev etal., Glass Technol., 46 28 (2005) an intensive band of Si – O – Si bridges of silicate net- [4] K.Choi et al., Waste Management 20 575 (2000) work at 1000 cm-1, 729 cm-1, and a band 1407 cm-1 of [BO3] groups which occur in its structure. The band
65 Condensed Matter Physics ANNUAL REPORT 2007
N-(2-AMINOPHENYL)-1-[(1S,2R)-2-HYDROXY-7,7- DIMETHYLBICYCLO[2.2.1]HEPT-1-YL]METHANESULFONAMIDE, A NEW LIGAND FOR ASYMMETRIC TRANSFER HYDROGENATION J. K. Maurin1, A. Krukowski, Z. Czarnocki 1 1Institute of Atomic Energy 2University of Warsaw, Department of Chemistry, Warsaw, Poland Asymmetric transfer hydrogenation (ATH) has be- (O2) is active as an acceptor for two weak O1-H10···O2 come a highly powerful, versatile and practical tool for and N2-H2B···O2ii hydrogen bonds, the first of them stereoselective synthesis of non-racemic secondary being intramolecular, whereas the second is an intermo- i alcohols and amines from their prochiral substrates such lecular bond. The remaining N1—H1···O3 intermolecu- as ketones or imines. Several effective ligands have lar hydrogen bond links the sulfonoamide N1—H1 been introduced, including a variety of β-amino alcohols hydrogen and S1=O3 oxygen of adjacent twofold scre- and 1,2-diamino compounds [1,2,3,4]. These ligands waxis-related molecules. These chains of molecules, in form coordinatively saturated 18-electron chiral Ru(II) the b-axis direction and visible easily in Fig. 2, are ii complexes when reacted with a ruthenium pre-catalyst, linked together by weaker N2—H2B···O2 hydrogen 6 such as [RuCl2(η -mesitylene)]2, that serve as promoters bonds, forming sheets of molecules parallel to (110). for stereoselective reduction of prochiral compounds The in-plane molecules are arranged so that their hydro- with usually extremely high efficiency. The present phobic parts point towards the surface. The interior of study is a part of our programme aimed at the construc- such sheets has more hydrophilic character. The view of tion of new ATH catalyst ligands. We report here the crystal packing is shown in Fig. 2. crystal and molecular structure of a new ligand, derived from (+)-camphor [5]. The absolute configuration of the title compound was known, since the compound was derived from an optically active fragment of known configuration. However, it was additionally confirmed by exploiting anomalous dispersion effects through the refinement of the Flack [6] parameter. Hence, we con- clude that the title compound has configuration S,R,R at the C1, C2 and C4 chiral centres, respectively. The title molecule (see Fig. 1) has four classical hydrogenbond donors: O1—H10, N1—H1, N2—H2A and N2—H2B, of which three are effectively used in either inter- or intramolecular hydrogen-bond formation with good hydrogenbond acceptors.
Fig. 2. Crystal packing shown along the c-axis. The hydrogen bonds are shown as the dashed lines.
References [1] M. Yamakawa et al., Angew. Chem. Int. Ed. 40 2818 (2001) [2] T. Hamada et al., Org. Lett. 4 4373 (2002) [3] C. Bianchini et al., J. Mol. Catal. A 132 13 (1998) [4] A.S.Y. Yim, M. Wills, Tetrahedron, 61 7994 (2005) [5] J.K. Maurin et al., Acta Cryst. E63 1593 (2007) [6] H.D. Flack, Acta Cryst. A39 876 (1983)
Fig. 1. Conformation of the molecule. The non-hydrogen atoms are shown as 30% probability ellipsoids.
Here, the sulfonoamide O atoms bound to the S atom serve as the acceptor functions. The two O atoms, however, form slightly different linkages – one of them
66 ANNUAL REPORT 2007 Condensed Matter Physics
SYNTHESIS AND ANTI-HIV STUDIES OF 2-ADAMANTYL- SUBSTITUTED THIAZOLIDIN-4-ONES J. Balzarini1, B. Orzeszko2, J. K. Maurin3, A. Orzeszko4,5 1Rega Institute for Medical Research, Katholieke Universiteit Leuven, Leuven, Belgium 2Warsaw University of Technology, Department of Chemistry, Warsaw, Poland 3Institute of Atomic Energy 4Agricultural University, Institute of Chemistry, Warsaw, Poland 5Military University of Technology, Warsaw, Poland Thiazolidin-4-ones have been reported to posses the (+)-22 isomer was responsible for the most potent a wide range of biological activities including antibacte- anti-HIV-1 activity with an EC50 value of 0.178 µM, rial (inhibitors of the bacterial enzyme MurB) [1], anti- while the levo isomer was over sixty-fold less active. tuberculosis [2], antitumor [3], antihistaminic (H1 an- The obtained from the X-ray studies molecular structure tagonist) [4], and anti-inflammatory (COX-1 inhibitors) of the camphoresulphonic acid salt of (-)-22 is shown in [5] or anticonvulsant activity. Fig. 1. Several 2,3-diaryl-1,3-thiazolidin-4-ones have proved to be particularly effective non-nucleoside HIV reverse transcriptase inhibitors (NNRTIs). Barecca et al. [6] have stated that these compounds may be considered as an “open model” of previously described 1H,3H- thiazolo[3,4-a]benzimidazoles (TBZs) because they contain necessary pharmacophoric elements of those HIV-1 NNRTIs, namely: a benzene-fused ring, an aryl group at C-1 and the nitrogen atom of the thiazole nu- cleus. Structure-activity relationship (SAR) studies have showed that the anti-HIV activity depends strongly on the nature of substituents at C-2 and N-3 of the thia- zolidinone ring.
A series of novel thiazolidin-4-ones bearing the lipophilic adamantyl substituent at position 2, and re- spective substituents on the nitrogen atom in the thia- Fig. 1. The molecular structure of the camphoresulphonic salt zolidine ring, were synthesized. It was found that sev- of (-)-22. The independent part of the unit cell consist of the amine cation part and the camphore sulphonic eral compounds exhibited a modest anti-HIV-1 activity, acid anion. The non-hydrogen atoms are shown as 30% while (±)-2-adamantan-1-yl-3-(4,6-dimethyl-pyridin-2- probability ellipsoids. yl)-thiazolidin-4-one 22 was endowed with a remark- able antiviral potency (EC50 = 0.35 µM) [7]. The ada- References mantane moiety played an important role in an eventual [1] C. J. Andres et al., Bioorg. Med. Chem. Lett. 10 715 antiviral activity of the compound. This compound (2000) behaved as a typical non-nucleoside reverse transcrip- [2] K. Babaoglu et al., Bioorg. Med. Chem. Lett. 13 3227 tase (RT) inhibitor with non-competitive inhibition (2003) [3] S. Grasso et al., Farmaco 43 851(1988) against RT with respect to the substrate (Ki = 12 µM). [4] M. V. Diurno et al., J. Med. Chem 35 2910 (1992) For this compound separation of the enantiomers via [5] G. C. Look et al., Bioorg. Med. Chem. Lett. 6 707 diastereoisomeric salts was performed. X-ray studies (1996) taking into account anomalous dispersion effect [8] [6] A. Rao et al., Antivir. Res. 63 79 (2004) enabled us to ascribe the S configuration to (–)-2- [7] J. Balzarini et al., Eur. J. Med. Chem. 42 993 (2007) adamantan-1-yl-3-(4,6-dimethyl-pyridin-2-yl)- [8] H.D. Flack, Acta Cryst. A39 876 (1983) thiazolidin-4-one (-)-22. Furthermore, it was found that
67 Condensed Matter Physics ANNUAL REPORT 2007
ENERGY DECOMPOSITION ANALYSIS AND ECTRON DENSITY CHARACTERIZATION OF HETEROCYCLIC DIMERS INTERMOLECULAR INTERACTIONS B. Paluchowska Institute of Atomic Energy The RHF/6-31++G(d,p) and MP2/6-31++G(d,p) … calculations for a series of Ocarboxyl-H Ocarboxyl, … … … C-H Ocarboxyl, C-H Xheteroring, Ocarboxyl-H Xheteroring (where X=O,S) hydrogen- and dihydrogen-bonded systems have been carried out in order to analyze the electron density distribution at the respective energy- optimized bond critical points. Binding interactions were calculated as a difference between the energy of dimer geometry AB and the energy of the two mono- mers A and B calculated at monomer equilibrium ge- ometries. Energies have been corrected for the basis set superposition error (BSSE). The difference electron density maps are provided to visualize character of the interaction (positive density is drawn with solid lines and negative with broken lines).
Fig. 2. Stacking π-π interactions. Cutoff is at 0.025 e/bohr3; contour-line spacing is 0.001 e/bohr3.
The third group of energetically favorable confor- mations proved to be motifs which exhibit the C-H···-π interactions (Fig. 3). The binding energy ranges from - 3.84 to -2,61 kcal/mol.
Fig. 1. In plane difference density distribution. Cut-off is at 0.025 e/bohr3; contour-line spacing is 0.05 e/bohr3.
Calculations were performed for several 2 and 3-furancarboxylic acids (2 and 3-FCA) and 2 and 3-thiophencarboxylic acids (2 and 3-THCA) dimer models indicating various binding forces. They revealed the predominant role played by the in plane Ocarboxyl-- … H Ocarboxyl type contact leading to cyclic C2h motifs (Fig. 1). In this group the calculated interaction energies range from -24,82kcal/mol in the case of thiophene Fig. 3. C-H…π interactions. Cutoff is at 0.025 e/bohr3; carboxylic acid dimers to -18,95 kcal/mol in the case of 3 furancarboxylic acid dimers. contour-line spacing is 0.001 e/bohr . Much weaker, but also significant interactions, are The attractive interaction in the perpendicular ar- stacking forces between heterocyclic rings (π-π interac- rangement (Fig. 3) is the cause source of preference for tions of energy from -6,27 to -3,84kcal/mol)-. Fig. 2. the herringbone structure in real crystals of the studied molecules.
68 ANNUAL REPORT 2007 Condensed Matter Physics
INTERMOLECULAR INTERACTIONS OF HETERORING OXYGEN AND SULPHUR BY FINGERPRINTS OF HIRSHFELD SURFACE B. Paluchowska Institute of Atomic Energy
The Hirshfeld surfaces [1] shape (Fig. 1) have been The de.and di reflect the most immediately useful constructed for the dimeric motifs of furancaroxylic property to map onto the surface. acids (2- and 3-FCA), and thiophencarboxylic acids (2- Where atoms make intermolecular contacts closer and 3-THCA) to visualize the interactions between than the sum of their van der Waals radii, these contacts molecules. Their characteristics served to encode differ- will be highlighted in red on the d and d surface This ent structural properties and intermolecular contact i e property provides an immediate picture of the nature of distances. intermolecular contacts in crystal.
Fig. 1. Hirshfeld surface on 2-THCA.
The two-dimensional mapping called ‘fingerprint’ plots were prepared according to Spackman and McKinnon [2] using CrystalExplorer package [3]. It summarizes quantitatively the nature and the type of intermolecular interaction experienced by a molecule in the bulk, and presents it in a convenient graphical for- mat. The mapping plots of the fraction of points on the Fig. 2. Fingerprint plot produced from the Hirshfeld surface surface are a function of the closest distances from the on 2-FCA molecule representing C-O contacts. point to a nuclei inside and outside the surface. In this manner all interaction types (hydrogen bonding, close The Fig. 2. shows fingerprints of C-O kind of in- and distant van der Waals contacts, C–H···π interactions, teractions within the examined dimmers. These kind of π – π stacking) are readily identifiable, and it becomes a plots correlate their several most obvious features with straightforward matter to classify molecular crystals by short and long intermolecular contacts within the crys- the nature of interactions, when examining crystal pack- tal. The stripe roughly along the diagonal reflects a large ing diagrams. fraction of points on the Hirshfeld surfaces that involves nearly head-to-head H···H contacts (i.e. a nearly linear In order to visualize the properties of the a mole- C–H···H–C orientation) between neighbouring mole- cule on the Hirshfeld surface the two parameters de and cules. d are defined i - de is the distance from the Hirshfeld surface to the nearest nucleus outside the surface References - di is the corresponding distance to the nearest nu- [1] F.L. Hirshfeld, Theor. Chim. Acta, 44, 129 (1977) cleus inside the surface. [2] M. A. Spackman, J. J. McKinnon, CrystEngComm, 4, 378 (2002) [3] S.K. Wolff, et al., CrystalExplorer 2.0 program
69 Condensed Matter Physics ANNUAL REPORT 2007
DIFFRACTION DATA AND MICROSTRUCTURE OF Al2O3 – SiO2 COATINGS L. Górski1, A. Pawłowski2 1Institute of Atomic Energy 2Institute of Metallurgy and Material Science PAS, Kraków, Poland The recent studies concern coatings of thermal bar- pattern (Fig. 2b) corresponds to the area marked on the rier type containing composites belonging to the system microscopic image (Fig. 2a). Al O – SiO system. In this system only one common 2 3 2 In the coating body mainly polycrystalline layers phase - mullite, with the approximate formula 3·Al O – 2 3 with some local discrepancies in chemical and phase 2·SiO , exists [1]. Mullite crystallizes in the orthorhom- 2 composition are observed. These effect due to plasma bic system with the lattice parameters: spray process conditions, which are far from the ther- a =7.546 Å, b = 7.690 Å, c = 2.884 Å, and the space modynamic equilibrium. group – Pbam [2]. The microstructure observed for coatings contain- X-ray diffraction patterns determined before and ing Al O – SiO composites is similar to that found in after plasma spraying are consistent with the mullite 2 3 2 previously studied coatings based on Al O and ZrO , structure. One can observe, however, some differences 2 3 2 though with some remarked differences [3,4]. in several peak intensities which may result from polytypism. Intensities on the coating pattern (Fig. 1b) Further studies aimed at the detailed description of are closer to those given in [2]. the coatings’ morphology and its dependence on ther- mal treatment are still in progress.
D
a a
250
200
150
counts 100
50
0 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 61 63 65 67 69 71 73 75 77 79 b 2 theta Fig. 2: a – TEM image from an area near the ceramics-metal b boundary, b – electron diffraction pattern from the area D marked red in (a) Fig. 1. Diffraction patterns Al2O 3 – SiO2 composite, Cu radia- tion;a -powder before spraying, b- coating as sprayed. References [1] R.F. Davis, J.A. Pask, J. Am. Cer. Soc., 55 525 (1972) The coating structure in nanometric scale was stud- [2] Powder Diffraction File System, Ver. 2.2, 15-776 ied by transmission electron microscopy (TEM) com- [3] A. Pawłowski et al., Arch. of Metallurgy and Materials, bined with electron diffraction on selected areas. 47 400 (2002) Specimens are were prepared by focused ion beam mill- [4] L. Górski, A. Pawłowski, Solid State Phenomena, 130 ing. The existence of alternate layers amorphous, nano- 297 (2007) and polycrystalline layers has have been observed. Amorphous layers are were visible near the metal – ceramics boundary (Fig. 2). The electron diffraction
70 ANNUAL REPORT 2007 Condensed Matter Physics
EVIDENCE FOR IMPLANTATION INDUCED CHANGE OF THERMO-RESISTANE PROPERTIES OF MANGANIN UNDER HIGH PRESSURE R. Wiśniewski1, B. Słowiński1,2, A.Yu. Didyk3, T. Wilczyńska1 1Institute of Atomic Energy 2Physics Faculty, Warsaw University of Technology, Warsaw, Poland 3Joint Institute for Nuclear Research, Dubna, Russia It is well known, that any changes of electric char- description of the temperature dependence of the sample acteristics of metals and alloys are hard to achieve by electrical resistance: using implantation techniques at moderate doses. Such a R = R [1+ a(T − T )2 ] problem arises, when one tries to improve thermal sta- max Rmax bility of the manganin based high-pressure sensors [1]. In our research the pressure and temperature sensitivi- yielding broader maximum that occurs in R dependence ties of manganin foil after high-dose implantation with on T. 253 MeV Kr ions (at surface dose of 2.5·1015 ion/cm2), as well as 250 keV Bi ions (1017ion/cm2) and 250 keV Kr ions (1016 ion/cm2) have been studied. As the result of the performed studies further experimental confirma- tion of our previous observations on the increase in manganin resistivity produced by high-dose implanta- tion [2, 3] was found. Moreover, applying irradiation with a dose of two orders of magnitude higher than earlier [1-3] two important practical effects have been Fig.1. Qualitative picture of the temperature dependence of established with the reliability much beyond the error the absolute value of the deviation of the manganin bars. First, the pressure sensitivity increased from α = sample resistance from the maximum. -5 -1 (2.45±0.01)·10 MPa before implantation to αimp = (4.60±0.01)·10-5 MPa-1 after implantation with 250 keV References Kr at the dose of 1016 ion/cm2. Second, the appreciable [1] B. Słowiński, R. Wiśniewski, JINR Comm. E14-89, 512 reduction of the temperature sensitivity of manganin as 1-6, Dubna (1989) the high-pressure sensor was attained [4]. [2] B. Słowiński et al., Nukleonika, 44 227 (1999) [3] T. Wilczyńska et al., Vacuum 78 515 (2005) The reduction of the temperature sensitivity can be [4] R. Wiśniewski et al., Vacuum 81 1199 (2007) described as decrease of a coefficient in the simplified
71 Condensed Matter Physics ANNUAL REPORT 2007
PROPERTY OF MANGANIN AFTER HIGH DOSE Ti AND Kr IMPLANTATION T. Wilczyńska1, R. Wiśniewski1, V. Semina2, A.Yu. Didyk2 1Institute of Atomic Energy 2Joint Institute for Nuclear Research, Dubna The main purpose of the present work was im- resistivity of manganin implanted with Kr ions increases provement of the thermoresistance properties of man- by 10% [2]. ganin gauges by ion implantation. The studied samples were 20 gauges produced by Dynasen Corp. in the form of planar structures containing of 2.5 µm thick 21.4 manganin layer [1]. The manganin layer was initially non-implanted 16 -2 ] 21.3 implanted with 60keV energy Ti ions (10 cm ) and Ω then with 250MeV Kr ions (1013 Kr cm-2). The maxi- mum penetration range of Ti ions estimated with the 21.2 TRIM code is 50nm. In the Kr ion implantation a 13µm thick special protection foil was used. The TRIM calcu- Resistance [ 21.1 lations indicate that Kr ions are distributed uniformly with density of 4·1018cm-3 all over the manganin layer. 21 We have assumed that during Kr implantation the Ti 0 50 100 150 200 ions were transferred deep into the manganin layer up to Temperature [°C] a depth of 0.5µm. The implanted sample can be mod- eled by two adjacent layers: the 0.5 m thick surface a layer with high Ti atoms content and the 2 m thick one 19.60 containing Kr atoms. Ti+Kr implanted ] Ω
19.55 Resistance[
19.50 0 50 100 150 200 Temperature [°C]
b Fig. 2. Temperature dependence of the Dynasen manganin Fig. 1. Model of ion distribution in implanted manganin sam- gauges resistance before and after ion implantation. ple. Since the concentration of the Kr and Ti atoms in The temperature behavior of the electrical resis- implanted layer is very large ~1022 cm-3, one can expect tance of the Dynasen gauges before and after ion im- significant changes in other characteristics of the sam- plantations was studied for temperatures within the ple. Further studies will concern the pressure and strain 20 - 220ºC range (Fig. 2). The resistance of Dynasen sensitivity of implanted gauges. specimen at room temperature after implantation de- creases from 20 ohms to 17 ohms. It means that the sample layer containing the Ti and Kr atoms has much References smaller electrical resistivity than the layer containing [1] T. Wilczyńska, R. Wiśniewski, unpublished only Kr atoms. Using our model of the sample (Fig. 1), [2] T. Wiczyńska et al., Vacuum, 78 515 (2005) [3] R. Wiśniewski, T. Wilczyńska, Materials Science 13 10 we found that the electrical resistivity of the material (2007) implanted with Ti and Kr ions decreases by about 40% with respect to the non-implanted material [3]. The strong influence of Ti ions on the electrical conductivity of manganin should be noticed since it is known that the
72 ANNUAL REPORT 2007 Condensed Matter Physics
HIGH PRESSURE EFFECTS IN CASTOR AND RAPE OIL R. Wiśniewski, T. Wilczyńska Institute of Atomic Energy Almost twenty years ago the new high-pressure 100 castor oil phase has been discovered [1] and quite re- ) % cently the similar phase was found for rape [2] and soy (
e 80
[3] oil. The oils are composed of triglycerides of differ- c n a ent fatty acid (triacylglycerols) and their molecules are t 60 t of rod-shaped. Their phase diagrams plotted in the tem- i m perature – pressure plane contain the specific region s 40 n a
where the change to a high pressure phase is possible r
t 20 (Fig. 1). 1 0 300 500 700 900 1100 wave length(nm) ] SOLID Fig. 2. The light transmission spectra for castor (red) and a HP phase
P rape oil (blue). The lower curves refer to the samples
G 0.5 before the high pressure treatment. [
P The very large hysteresis in volume change is ob- LIQUID served during pressure changes for castor oil. Similarly, in the case of rape oil after the first cycle of investiga- 0 tion no reversible change in volume were noticed -40 -20 0 20 40 (Fig. 3). T [°C]
Fig. 1. Sketch of T-P phase diagram for castor, rape and soy oil. The lines are the solid – liquid phase boundaries. The ellipsoidal shapes denote regions where transfor- mation to high pressure phase occurs. The red color corresponds to castor oil; blue and green, to rape and soy oil, respectively.
The formation of the high pressure phase was de- tected in the light transmittance measurements before and after the appropriate high pressure treatment. The large increase (from 70 to 95%) in the castor oil trans- mittance was recorded in the wavelength region of 300-
1100 nm (Fig. 2). However, no such large effect was found for the rape oil. The 0.4% increase in the castor Fig. 3. Relative volume changes of rape oil during the pres- oil density after the high pressure phase might account sure cycle from normal conditions followed by increase in pressure (370 MPa, 48h) to induce the phase transi- for the observed change in the light transmittance. tion, and then decrease of pressure to normal condi- In order to study the possible changes in chemical tions. composition of the oil samples during pressure treat- ment various high efficient chromatography methods (GLC, HPLC-PR and HPSEC) were used. Slight de- References [1] M. Siegoczyński et al., High Pressure Res. 1, 225 crease (from 83.63 to 82.61%) in the content of the (1989) main component was found. [2] A. Rostocki et al., J. Mol. Liq., 135 120 (2007) The Raman spectra investigation for castor oil re- [3] A. Rostocki et al., High Pressure Res., 27 43 (2007) vealed a change of 3931 cm-1 line. However, no such change in the rape oil Raman spectra was observed.
73 Condensed Matter Physics ANNUAL REPORT 2007
MODELLING OF BEAM EXTRACTION FROM HOLLOW CATHODE ION SOURCES M. Turek1, K. Pyszniak1, A. Droździel1, D. Mączka2, J. Sielanko3 1Institute of Physics, Maria Curie-Skłodowska University, Lublin, Poland 2Institute of Atomic Energy 3Institute of Computer Science, Maria Curie-Skłodowska University, Lublin, Poland
Detailed knowledge of processes occurring during 9 ion beam extraction is indispensable in applications like 8 ion implantation, lithography, micro-analysis, plasma 7
] 6
heating, ion thrusters and many others. 2 5 simulation [ mm[ The beam extraction is commonly described with 4 fit
m m 1/2 S y(x) = a+b*x the Child-Langmuir ’’3/2’’ formula, derived for flat 3 electrodes diode [1]. The formula has been modified for a = 0.89 2 spherical and cylindrical systems [2], and corrections b = 1.09 1 for the initial velocity have been introduced [3]. Al- 0 though, the Child-Langmuir formula describes properly 0 10 20 30 40 50 U [ kV ] charge limited flows [4], it neglects many important e factors like variable area and shape of the plasma me- Fig. 2. Plasma meniscus surface as a function of U. niscus; focusing effect of the meniscus; limitations of the ion flow into the extraction area caused by finite The calculated current-voltage characteristics are plasma density; geometry of extraction hole. All of the not linear in the (U3/2,I) coordinates. The deviations factors may cause deviations from ’’three halves’’ law from the ’’3/2’’ law can be desribed by the dynamical like linear current-voltage dependence [5] or the current perveance defined as: saturation [6]. = ( 2/3 ) Pd dI / d U In our study we have employed the TRQR code [7] based on the particle-in-cell (PIC), to simulate the beam The dependence of Pd on U yielded by the simula- extraction process in simple model of hollow cathode tions is very similar to that obtained from experimental ion source. The code treats charged particle behavior in measurements [8,9]. a self-consistent manner, taking into account space- d =10 mm charge of plasma and extracted beam. Plasma meniscus 0.00020 r = 4 mm r = 5 mm formation, evolution of potential distribution and cur- r = 6 mm rent-voltage curves were studied. 0.00015
r = 6 mm 0.00010 400 [a.u.] d P
300 0.00005 r = 5 mm
200 0.00000 0 2000000 4000000 6000000 8000000 10000000 12000000 I [a.u.] U3/2 [ V3/2 ] r = 4 mm 100 Fig. 3. The dependence of perveance Pd on extraction voltage.
0 0 2000000 4000000 6000000 8000000 10000000 References U3/2 [ V3/2 ] [1] H. Zhang, Ion Sources, Springer, Berlin (1999) Fig. 1. Current-voltage curves for different hole sizes. [2] G.D. Alton, Nuclear Instr and Meth B 189 15 (1981) [3] R.R. Puri et al. Physics of Plasmas, 11 1178 (2004) [4] W.L. Rautenbach, Nuclear Instr and Meth B 12 96 Simulations were peerformed for different: diame- (1961) K. Shinto et al., Rev of Sci Instr, 77 512 (2006) ters of extraction hole, extraction electrode–extraction [5] M.C. Vella et al., Ion Implantation Technology 5 27 hole distances and plasma temperatures. Current-voltage (2000) curves of the form I~U3/4 were obtained (Fig. 1). The [6] P. Suominen et al., Proc. of the 15th Int. Workshop on dependency of plasma meniscus surface and shape on ECR ion sources, Jyväskylä, Finland, 12-14 June (2002) extraction voltage were also investigated (Fig. 2). [7] M. Turek et al., Vacuum.78 649 (2005) [8] M. Turek et al., AIP Conf. Proc. 812 15 (2006) [9] K. Pyszniak et al., Instruments and Experimental Tech- niques 50 552 (2007)
74 ANNUAL REPORT 2007 Condensed Matter Physics
SPUTTERING OF Ti TARGET WITH MEDIUM ENERGY Ar+ BEAM K. Pyszniak1, M. Turek1, A. Droździel1, D. Mączka2, J. Sielanko3 1Institute of Physics, Maria Curie-Skłodowska University, Lublin, Poland 2Institute of Atomic Energy 3Institute of Computer Science, Maria Curie-Skłodowska University, Lublin, Poland The emission of secondary ions and electrons from One aim of the study was to determine the optimal + Ar bombarded Ti target has been studied. In experi- Ue value for the best resolution measurements of secon- ments the system designed for medium energy ion beam dary ion mass spectra. The optimal Ue value results sputtering was used [1,2]. The Ar+ kinetic energy varied from secondary ion current – mass spectrum resolution in the range of 20-30 keV. The primary beam current trade-off. µ 2 density was 0.7 A/cm 200 + The secondary ions energy spectra determined for 180 Ar Ti 160 different values of the voltage, Ue, between the target 140 and energy filter entrance is a smooth single-maximum 30 kV 120 distribution (Fig. 1). The expected increase of the sec- [pA] 100 e e I ondary ions current with increasing Ue is also observed 80
(Fig. 2). 60
1000 40 20 kV + 30 keV Ar Ti 3 20 1) U =60V e 0 2) U =80V 0 20 40 60 80 100 120 e 750 E [eV] 3) U =100V e 2 Fig. 3. Energy spectra of secondary electrons emitted from Ti 1 target.
[pA] 500 j I Since titanium has five well-distinguishable iso- 250 topes the Ti target is especially useful for estimation of mass spectrum resolution. It was found that satisfactory mass spectra resolution (R=185) and large secondary 0 0 50 100 150 200 ion current was achieved for Ue = 90 V (Fig. 4). E [eV]
Fig. 1. Energy spectra of secondary ions emitted from Ti + 20 keV Ar -> Ti target irradiated by Ar+ beam. 2.00E-009 U = 120 V e U = 110 V 1600 1.50E-009 e U = 100 V 1400 e U = 90 V e
1200 ] [ A j U = 80 V I 1.00E-009 e 1000
800 [ pA ] pA [ + 5.00E-010
max 600 I Ar Ti 400 20 keV 30 keV 200 0.00E+000 44 45 46 47 48 49 50 51 52 0 m [ j.m.a ] 40 60 80 100 120 140 160 180 200 U [ V ] e Fig. 4. Mass spectra of secondary ions. Fig. 2. The dependence of maximal secondary ion current on extraction voltage. Similar studies have been performed for Si targets [3]. References The energy spectra of secondary electrons emitted + [1] A. Drozdziel et al., Rapid Commun. Mass Spectrom.20 from titanium target for different energy of incident Ar 298 (2006) ions are also one-maximum distributions (Fig. 3). The [2] K. Pyszniak et al., Vacuum 81 1145 (2007) measurements of the dependence of the secondary elec- [3] K Pyszniak et al., Elektronika 10 51 (2007) tron current on Ue. show that Ue equal to 20-40 V is sufficient to get rid of most of the secondary electrons reaching the energy filter.
75
ANNUAL REPORT 2007 Nuclear Techniques in Health and Environment Protection Management of Hazards
CENTRE OF EXCELLENCE MANHAZ – MANAGEMENT OF HEALTH AND ENVIRONMENTAL HAZARDS
The EU Centre of Excellence MANHAZ (Man- Warsaw. The consortium of institutions began realisa- agement of Health and Environmental Hazards) was tion of the project in the mid of 2006. The Institute of established in 2003 in the Institute of Atomic Energy in Atomic Energy is responsible for two parts of the sys- Świerk. tem dealing with modelling of radiological and chemi- cal. The radiological part is being implemented jointly The mission of the Centre of Excellence with the Material Research Laboratory of the Institute MANHAZ is to provide leadership, expertise and inte- of Atomic Energy. gration of efforts related to risk assessment of activities involving hazardous substances in Poland. The main The main objective of the project is the deve- areas of activities CoE MANHAZ cover variety of lopment of a prototype of the new advanced, integrated problems related to development and practical imple- system of modules and data that: mentation of recommended methodologies, procedures - determines emergency zones based on simulations guides, computer programs and data bases for the fol- of the dispersion of hazardous nuclear, biological, lowing four groups of problems: and chemical materials released to the atmosphere 1. Management of major accident hazards – advanced and water bodies in urban areas, tools and information systems for supporting au- - provides essential information on required resour- thorities in the management of risks and emergency ces, such as search and rescue teams, equipment, situations due to technological hazards. medical assistance, food, evacuation and shelter, 2. Management of chemical hazards relating to emis- needed in case of emergency situation, sion of chemicals, their transport and transforma- - has access to all the necessary databases and GIS- tion in the environment, environmental and health based information, which can be distributed geo- risk assessment: models, data bases, stand alone graphically among different urban services, computer programs and systems for health and en- - enables co-ordination of emergency action in real- vironmental risks assessment and decision making. time based on reliable system for information ex- 3. Risk assessment of fuel cycles of electrical power change and interoperability capabilities among generation, including externalities. different systems. 4. Tools for radiological risk assessment and decision The MANHAZ Centre acts also a Technical making for close and distant accidents. Support Organization for the Centre for Radiological The Centre is getting involved in a number of pro- Events of the National Atomic Energy Agency and is jects on infrastructure security management in Poland. involved in the integrated project EURANOS “Europe- In particular it concerns: an approach to nuclear and radiological emergency - development of computer aided decision support management and rehabilitation strategies”. system for crises management in the agglomeration The staff of the Centre has been also engaged in of Warsaw; the development of environmental systems for man- - customization of existing methodologies for securi- agement of air quality. ty vulnerability assessment of chemical installa- tions in Poland; References - GIS based decision support systems for crisis ma- [1] MANHAZ Monograph, Models and techniques for naging chemical, radiological or terrorist emergen- health and environmental hazard assessment and man- agement, Otwock (2006) cies – cooperation with the National Defence [2] M. Borysiewicz et al., IAE Report B–30 (2006) (in University. Polish) In 2007 one of the most important tasks of the [3] M. Borysiewicz et al., IAE Report B–31 (2006) (in Polish) Centre was related to the participation in the national [4] M. Borysiewicz et al., IEA Report B–22 (2007) (in project on: Hazard models for urban agglomeration Polish) and crisis management system exemplified by the city
79 Nuclear Techniques in Health and Environment Protection ANNUAL REPORT 2007 Management of Hazards
SYSTEM SECURITY RISK ANALYSIS M. Borysiewicz Institute of Atomic Energy The industry and operators of various element of Threat-based approaches focus on how an adversa- critical infrastructure face the important need to assess ry could exploit technical aspects of a system (e.g., whether current security measures effectively address inherent vulnerabilities, poor configuration of key com- the new and unforeseen threats, and make enhance- ponents), as well as non-technical aspects of the sys- ments as required to provide for the safety of the public, tem’s operational environment, to produce adverse workers, and the environment. Security risk manage- effects. Analysis, rather than assessment, predominates ment involves the systematic identification, analysis, in a threat-based approach. treatment (e.g., mitigation, acceptance, transfer), moni- Asset-based approaches focus on the assets that toring, and communication of risk. Key components of must be protected from threats. An asset-based appro- a security risk management process are risk analysis, in ach includes identification of system components, as which a system, its components, and their relationships well as analysis of their interconnections and depen- are analyzed with respect to threats and vulnerabilities; dencies. risk assessment, in which the level of risk is determined based on analysis and a well-defined approach to identi- Mission- or objective-based approaches focus on fying and assigning values to risk factors, including the missions or business objectives that must be possible consequences or impacts of threats; and risk achieved, despite the presence of threats. A mission- communication, in which the results of a risk as- based approach includes identification of business func- sessment are translated into terms that are meaningful tions and how those functions relate to (e.g., depend to decision-makers. upon, impose requirements on) systems and their be- havior. Security incidents are intentional, rather than acci- dental, which is a key basis to understanding the haz- The an analytical portion of these approaches is cal- ards, likelihood, and possible consequences. The risk led a Security Vulnerability Analysis (SVA). The lead- that is being analyzed to solve security issues is an ing institutions and organizations (e.g. Center for expression of the likelihood that a defined threat will Chemical Process Safety - CCPS) dealing with chemi- reach a specific vulnerability of a particular attractive cal process safety) created the SVA methodology to target or combination of targets to cause a given set of help companies to evaluate the vulnerability of their consequences. chemical sites to terrorist attack or other malicious acts. Methods available to SVAs can have varying scopes, The estimate of consequences may be different in varying levels of detail, and utilize different methods. magnitude or scope than is normally anticipated for accidental releases. In the case of security events, ad- The SVA approach can also applied to informa- versaries are determined (sometimes at all costs) to find tion/cyber security, where the objective of is to protect vulnerabilities and to maximize damage. In addition, critical information systems including hardware, soft- theft or diversion of chemicals is normally not conside- ware, infrastructure, and data from loss, theft, or dam- red in accidental release studies, but should be included age. In a chemical facility, protecting information and in security studies. computer networks means more than safeguarding a company's proprietary information and keeping the A second unique term of interest is vulnerability, business running, as important as those goals are. It also which is any weakness that can be exploited by an ad- means protecting chemical processes from hazardous versary to gain unauthorized access to an asset. Vulner- disruptions and preventing unwanted chemical releases. abilities can result from, but are not limited to, man- To an adversary, information and network access can agement practices, physical security weaknesses, or provide the power to harm the company, its employees, operational factors. and the community at large. A variety of approaches to system security risk A analysis of SVA methodologies and approaches analysis and risk assessment have been taken: to SVA based security management in chemical process Policy-based approaches focus on security requ- industry, the related information/cyber security and irements, as stated in organizational Policy documents, Industrial Control System were studied by the author, in or in applicable regulations or standards. Failure to the framework of the project on integrated methods for meet a requirement – typically, to implement a specific major accidents . risk and security implement in the safeguard – constitutes a potential source of risk. In period 2005- 2007 by the Central Institute of Labour a policy-based approach, the consequences of such Protection n Warsaw a failure are analyzed and assessed.
80 ANNUAL REPORT 2007 Nuclear Techniques in Health and Environment Protection Management of Hazards
POLLUTANT AIR CONCENTRATION PREDICTION SYSTEM FOR URBAN AGGLOMERATIONS M. Borysiewicz1, S. Potempski1 , W. Kacprzyk2 1Institute of Atomic Energy 2Institute of Environmental Protection, Warsaw, Poland The aim of the project 3 T09D 017 28 supported tices. The subsystems were developed for processing by the Ministry of Science and Higher Education and raw emission inventarisation data into input for given implemented in the period 2005 -2007 by the Institute computation grids for further processing in the atmos- of Environmental Protection in cooperation with the pheric pollutant transport and transformation modelling Centre of Excellence MANHAZ in the Institute of subsystem; A meteorological modelling subsystem (3), Atomic Energy was to develop an integrated pollutant implementing MM5 and WRF models for mezoscale air concentration prediction system for urban agglom- and local meteorological parameter forecasting, taking eration (SPSZP-Ag) for predicting air quality, analyz- into account the characteristics of urban areas; A trans- ing emission events and accidental releases and calcu- port and transformation modelling subsystem lating contaminant transport, including secondary con- PMTTZ/CMAQ (4) simultaneously taking into account tamination and analysis of selected areas, taking into many pollutants in air in many space scales, including account ozone, dust, NOx, SOx, heavy metals and haz- the urban agglomeration scale, enabling the simulation ardous substances. According to adopted assumptions, of all important chemical and physical processes influ- the SPSZP-Ag system was designed largely on the base encing the transport, transformation and deposition of of calculation systems developed for the U.S. Environ- pollutants in air using emission in meteorological mod- mental Protection Agency, namely CMAQ (transport els and adapting tools for microscale calculations calculations and pollutant transformation in the atmos- (ENVI-met model) and for the pollutant transport for phere) and SMOKE (source inventarisation and emis- street canyons (OSPAM program); An urban commu- sion calculations), as well as on the base of meteoro- nity health hazard estimation subsystem PON/APEX, logical models MM5 and WRF. linked with PMTTZ/CMAQ (5). The subsystem is based on the Pollutant Air Pollutants Exposure model ( State-of-the-art solutions for emission and trans- APEX) developed for the US EPA. The SPSZP-Ag port modelling and pollutant transformation calculation includes IO/API tools for input and output processing systems, as well as solutions for space information and for calculation results visualization (PAVE). techniques and integration of calculation models were implemented during the development of the SPSZP-Ag The SPSZP-Ag system enables to simultaneously system. The prototype software for the SPSZP-Ag sys- analyze emissions and transport for many pollutants in tem was implemented on the Beowulf cluster running many space scales (from local to urban agglomeration under the Linux operating system in the Centre of Ex- to regional), taking into account the coupling of trans- cellence MANHAZ and using the MPI package for port models and chemical transformations to the dy- parallel computing. namics of the atmosphere. SPSZP-Ag was used to simulate the pollutant distribution in air for selected The following five subsystems were developed in emission scenarios in the Warsaw agglomeration using the frames of the SPSZP-Ag system. Two versions of emission data delivered by the Mazovian Voivodeship emission modelling subsystems: an advanced one Environmental Protection Inspectorate. More informa- (EMS/SMOKE) (1) basing on the concepts and struc- tion on SPSZP-Ag is available at the Web site: ture of SMOKE and a simplified one (2), better suited http://www2.cyf.gov.pl/spszp-ag. for the present Polish emission inventarisation prac-
81 Nuclear Techniques in Health and Environment Protection ANNUAL REPORT 2007 Management of Hazards
THE SIMULATIONS OF EMERGENCY SITUATIONS CAUSED BY ACTS OF TERROR WITH THE USAGE OF TOXIC OR RADIOACTIVE SUBSTANCES IN URBAN AREAS M. Borysiewicz, L. Czerski, J. Dyczewski, I. Garanty, A. Kozubal, S. Potempski, A. Wasiuk, H. Jędrzejec, H. Wojciechowicz Institute of Atomic Energy The Centre of Excellence MANHAZ is engaged in The implementation of the subsystem for chemical a project aiming at the development of system for ma- emergencies will be based on the following elements: nagement of crisis situation arisen due to chemical or - databases of physical-chemical substances, radiological releases in urban areas [1]. - intervention levels linked to substances database, - basic scenarios for selected substances or groups A general concept for developing modules for of substances depending on the type of release, chemical and radiological emergencies is based on the storing and transportation conditions, following assumptions: - adaptive part of scenario depending on meteorolo- - the main aim of the simulation modules of chemi- gical conditions and localization of source of rele- cal and radiological emergency situation is deter- ase, mining emergency zones, taking into account po- - emergency simulator, ssible consequences for various types of hazards, - simulation results presented on digital maps in the - the simulators to determine emergency zones form of emergency zones. should be as fast as possible. The basic scenarios will be calculated using either Therefore the main idea is to include as many ele- the Unified Model for Pollutant Dispersion in Atmo- ments of the system as possible into databases from sphere (UPDMA) or well known Hazard Prediction and which they can be fast and easily extracted. To meet Assessment Capability (HPAC) code. In principle the these requirements, the system should contain as many basic approach is similar to that one used in the Off-site pre-defined scenarios as possible. In case of real emer- Consequence Analysis Guidance for the Risk Manage- gency these scenarios have to be adapted taking into ment Program, however it is significantly extended to account the current conditions. Such an approach ena- much greater number of different scenarios. All the bles fast estimation of emergency zones, however with results of pre-calculated scenarios with different mete- possible lost of precision. Nevertheless in emergency orological conditions taking into account a number of response context the most important is to determine the special parameterizations for urban agglomeration will areas where some countermeasures like evacuation or be stored in databases. It is also planned to carry out sheltering have to be applied as fast as possible. Secon- CFD (Computational Fluid Dynamics)calculations for a dly the databases will contain also information related set of particularly vulnerable locations of Warsaw in to decision making process like pre-defined tasks for order to verify the simplified approach. rescue teams linked to appropriate templates of crisis situation. This will allow building step by step The proposed approach depends on two factors: knowledge database, causing that the system can evolu- - the proper choice of basic scenarios (in particular tionally change its character from typical “command how many pre-calculated cases should be included and control” type to the expert system. into database), - the proper identification of crisis situation which Then for each type of hazard it is necessary: corresponds to good parameterization of pre- - to develop simulation module to make prognosis defined scenarios. of the situation, - to include into databases data requested to perform The solution is to build gradually huge enough da- simulations, tabases, which will be useful in the future. Analogously - to define decision templates and tasks for any approach will be applied for the radiological part of the rescue teams and urban services. system. Such a general approach allows for generalization References and unification of the logical model and utilization of [1] M. Borysiewicz et al., IAE Report B–22 (2007) some formal programming techniques. (in Polish)
82 ANNUAL REPORT 2007 Nuclear Techniques in Health and Environment Protection Management of Hazards
SPATIAL PLANNING OF PREVENTING AND ABATEMENT MEASURES IN THE CONTEXT OF MAJOR ACCIDENTS M. Borysiewicz Institute of Atomic Energy The report on “Spatial Planning of Preventing The Guidelines cover the following important top- and Abatement Measures” [1] with recommendations ics: role of land use planning in major accidents risk on Spatial Planning Measures and Land Use Plans fo- management, principles and consideration of additional cusing on issues of major industrial accidents was pre- technical measures, hazard and risk assessment meth- pared by M. Borysiewicz as a part of his involvement in odologies and criteria, database of land use planning the Rivershield Project [2] coordinated by the Institute scenarios and risk assessment data, modeling and end- of Environment Protection in Warsaw. The RIVER points as well as environmental risk assessment meth- SHIELD Project is implemented under the EU Com- ods. munity Initiative INTERREG III B CADSES The experts from the Lubuskie Region prepared Neighbourhood Programme by the Institute of Envi- an expertise on “Risk Analysis of the Major Industrial ronmental Protection (IEP) from Warsaw. The subject Accidents in the Lubuskie Region as the Element of the of the Polish part of this Project is the Oder River (the Documentation concerning the Spatial Planning”, Odra River) in the Lubuskie Region. It is expected that which together with the report on “Spatial Planning of the project will strengthen the capacity of emergency Preventing and Abatement Measures” will provide and environmental services engaged in the process rationales for proposals of modification of current land directed at the reduction of the effects of potential indu- use plans in the Lubuskie Region in Poland. strial accidents. References The report [1] consists of the Guidelines for Land [1] M. Borysiewicz, Spatial Planning of Preventing and Use Planning in the context of the Seveso II Directive Abatement Measures, Institute of Environmental Pro- and 4 attachments: tection, Warsaw (2007) A. Relevant Steps in Major Accidents Quantitative [2] M. Borysiewicz, W. Kacprzyk, The RIVER SHIELD Risk Assessment Process. Project – management of the risk form industrial water B. Environmental Risk Assessment. pollution, Environmental Protection and Natural Re- source, ser. 30 (2006) C. HSE's Current Approach to Land Use Planning [3] M. Borysiewicz, Proc. of International Seminar on (LUP) Policy and Practice. Industrial Accidents, 25-27 September 2007, Ustrzyki D. Planning Assessment Method Using Sensitivity Levels Dolne – Jedlicze, Poland and 2 D Decision Matrix for Land Use Planning.
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DIRECT COSTS OF NUCLEAR TREATIES, AGREEMENTS AND AGENCIES M. Borysiewicz, I. Garanty, A. Kozubal Institute of Atomic Energy The technical report [1] and the dedicated website: • Expanding the nonproliferation regime on a diffe- http://manhaz.cyf.gov.pl/manhaz/ind.php?ff=projects rent financial basis. IAEA Safeguards expenditures are the main tangible results of the project TW6-TRE- and resources. DICNT implemented in Centre of Excellence • EURATOM, including: Operation of the MANHAZ. EURATOM safeguards office; EURATOM safe- guards resources (budget, staff resources and safe- The contents of the technical report covers the fol- guards equipment). lowing groups of problems: • FUSION energy, including externalities and proli- • Inventory of International Nonproliferation Or- feration implications of thermonuclear-fusion ganizations & Regimes: International treaties; energy systems: Risk assessment of fusion rese- Treaties, conventions & agreements related to the arch; Technical points related to thermonuclear IAEA´s work; Treaties, conventions & agreements weapons and their proliferation; Nuclear Weapons under IAEA auspices; Safety & Security; Science Proliferation Issues of Thermonuclear-Fusion & Technology; Safeguards & Verification; Or- Energy Systems; Common proliferation implica- ganization & Cooperative Agreements. tions of all fusion energy systems; Neutron abun- • The safeguards system of the International Atomic dance: Fusion-fission hybrids and plutonium bre- Energy Agency including: Legal Basis of Agency eders; Tritium abundance: Boosted-fission and pu- Safeguards; Evolution of the Safeguards System re-fusion nuclear weapons; Dedicated nuclear we- 1991 – 2005; Measures to Strengthen the Safe- apons materials production facilities; Latent ther- guards System, 1991-2005. monuclear proliferation; Induced nuclear prolifera- • Problems of safeguards system implementation. tion; Specific proliferation implications of inertial • Safeguards current status. confinement fusion (ICF): Nuclear weapon-effects • Financing IAEA verifications of the NPT. research, Driving force of spin-off technologies, • Cost of implementation of nonproliferation regime Declassification and latent proliferation. in states including: U.S. Financial Support to Meet Safeguards Obligations of IAEA; US FY 2006 References Budget request for Defense Nuclear Nonprolifera- [1] M. Borysiewicz et al., IAE Report B–49 (2007) tion; Case of Poland.
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THE CALCULATION MODELS FOR ASSESSMENT OF TERRORIST THREATS IN AQUEOUS ENVIRONMENT AND URBAN POTABLE WATER DISTRIBUTION NETWORK M. Borysiewicz, Ł. Czerski, J. Dyczewski, I. Garanty, A. Kozubal, S. Potempski, A.Wasiuk, H. Wojciechowicz Institute of Atomic Energy The modeling two most essential cases of water equal to the sum of fluxes of the particulate and diluted contamination threat, the surface waters and the drink- toxicants at the bottom boundary. ing water distribution system was considered [1]. The The models were applied to dispersion and trans- general approach to modeling of contaminations port calculations of oil and sulphuric acid spills to the spreading in aqueous environment with one - and three- Wloclawek reservoir. dimensional models was also outlined. The latter is based on the idea of THREETOX code [2] and its fur- The report [1] discusses also computer programs ther extensions [3]. The code is used to simulate 3-D developed in the Centre of Excellence MANHAZ for hydrodynamics fields, suspended sediment and toxicant determination of concentration of pollutants in surface transport. The code includes a set of sub-models. The waters basing on simplified numerical models recom- hydrodynamics are simulated on the base of a three- mended by International Atomic Energy Agency [3]. dimensional, time-dependent, free surface, primitive The last part of the report presents modeling systems equation model. The model equations are written in for simulation of contamination dispersion in drinking Cartesian co-ordinates. The water body is assumed to water distribution net EPANET and EPANET-MSX, be hydrostatic and incompressible. The concept of eddy the latter is an extension to the original EPANET that viscosity/diffusivity and Prandtls hypothesis with the allows it to model any system of multiple, interacting variable turbulence length scale are used to define the chemical species [5]. These models can be utilized by turbulence stresses. At the free surface all fluxes (mo- crisis centers for quick assessment of threats caused by mentum, heat, etc.) are prescribed. At the bottom and release of toxic substances to potable water networks. the land boundaries the conditions of no diffusive flu- References xes of any property are used. The open lateral boundary [1] M. Borysiewicz et al., IAE Report B–52 (2007) (in conditions are modified radiation conditions. Polish) Three-dimensional advection-diffusion equations [2] N. Margvelashvily et al., Radiation Protection Do- simetry, 73 177 (1997) are used to simulate the toxicant transport in the water [3] International Atomic Energy Agency, Safety Reports column and an ordinary differential equation is applied Series, „Generic Models for Use of Assessing the Im- to simulate concentration of a toxicant averaged over pact of Discharges of Radioactive Substances to the the thickness of an upper exchangeable layer of bottom Environment”, Vienna (2001) deposition. The boundary conditions are: no flux of the [4] MANHAZ Monograph, Part III, Otwock (2006) toxicants concentration in solute and in the suspended [5] EPANET 2 Users manual, EPA/600/R-00/57 (2000) sediments through the water surface, and its flux is
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THE APPLICATION OF MM5 NUMERICAL WEATHER PREDICTION SYSTEM FOR HIGH RESOLUTION SIMULATIONS S. Potempski,1, 2 1Institute of Atomic Energy 2Institute for Environment and Sustainability, EC JRC, Ispra, Italy For the purpose of atmospheric dispersion models The best resolution of terrain, land use and vegeta- to be applied in urban areas either in case of accidental tion data sets is 30 sec, which correspond to about release of hazardous material into atmosphere or for 0.9 km (at middle latitudes). Then 1 km grid size is examining air quality it is absolutely necessary to have a reasonable choice for high resolution calculations. accurate meteorological fields in highest possible reso- This in turn means that it can be difficult to simulate lution. This can be obtained by applying a limited area some very local effects – like impact of the areas, numerical weather prediction model. One the most which shape doesn’t suit very much to the grid (for popular and mature models is mesoscale model MM5 example long and narrow lake). [1] developed by the Penn State University and NCAR There is a need for appropriate computer power as consortium. In order to use this model for high resolu- one can roughly estimate the time needed for making tion simulations it is necessary to have detailed data on simulations on n nested grid as proportional to the num- elevation, land use etc. and include special parameteri- ber of grid points times 3 to the (n-1) power. It should zation. The data of the resolution of 1 km are available be also stressed that putting more advanced physics from the US Geological Survey. In order to evaluate option makes it necessary to decrease time step to fulfil different types of parameterizations which can be used the Courant-Friedrich-Levy stability condition. in MM5 system CCU-CAML lidar measurements (in particular aerosol vertical profiles) performed at Ispra The MM5 modelling system has a possibility to station (Italy) [2] were utilized. In such a way estima- include observation data using nudging procedure. In tion of boundary layer could be done by means on me- particular it could be of some advantage to add infor- asurement and compared with the predictions obtained mation on vertical profiles. The problem is however from MM5 simulations. such, that requested data are often not available for the area of interest. In general coupling of observational A series of numerical simulations were performed data with high resolution numerical weather simulation to understand to which extent the lidar-detected evolu- is useful if the measured data have good frequency and tion of the particles distribution along the vertical could come from at least a few stations in the domain. In this be explained by the boundary layer and/or horizontal respect the drawback of used lidar station is that there transport processes. A particular stress was put on inve- are no nocturnal data. stigation of boundary layer parameters. The conclu- sions of the simulations can be summarized as follows: References [1] G. Grell et al., A Description of the Fifth-Generation Using MM5 and available data sets it is possible to Penn State/NCAR Mesoscale Model (MM5), investigate local phenomena in the atmospheric boun- NCAR/TN (1995) dary layer (like mountain breeze or ground inversion), [2] S. Potempski et al., Numerical weather simulations in but there are some obvious limitations related to the support to the CCU CAML Lidar measurements: pre- following aspects: liminary results for the case study of 21st September 2006 IES, Ispra, EUR 22855 (2007)
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APPLICATION OF THE ENSEMBLE SYSTEM TO ANALYSIS OF ETEX EXPERIMENT S. Potempski1,2, S. Galmarini2 1Institute of Atomic Energy 2Institute for Environment and Sustainability, EC JRC, Ispra, Italy The long-range tracer experiments ETEX [1], con- ENSEMBLE models or any other percentile, in terms ducted in the autumn 1994, were organized jointly by of statistical parameters (like factors of 2 or 5). Similar the European Commission, the World Meteorological analysis, with 15 models’ datasets, was also made for Organization and the International Atomic Energy ETEX-2 experiment. In comparison with ETEX-1, Agency. Two different releases of passive tracers where a good agreement with measurement data was (PMCH and PMCP respectively), known as ETEX-1 found, the analysis of the ETEX-2 case showed some and ETEX-2, took place in Rennes, France and a ne- essential discrepancies between the results of the mo- twork of detection stations covering the area from Swit- dels and observational data. zerland to Norway and from the United Kingdom to Additional analyses were also performed for a few Poland was established to find concentration fields. weighted models obtained from both ETEX-1 and Then a reliable set of measurement data was obtained, ETEX-2 datasets in addition to the median model. In which can be used in the validation and evaluation of particular the Bayesian Model Averaging (BMA) algo- long-range atmospheric dispersion models. In 1999 the rithm was applied to find the weights for the models, ENSEMBLE project [2] was set out to addresses har- corresponding to the probabilities that the model is the monization and coherence issues for emergency man- closest one to the observation data. In these analyses 25 agement and decision-making in relation to long range and 15 models’ results were used for ETEX-1 and atmospheric dispersion modeling. ETEX-2 respectively. The participants of the ENSEMBLE project count Relatively good agreement has been found for the most European Meteorological Institutes and national models based on the BMA schemes applied to two responsible emergency organizations in addition to distinct ETEX experiments. Additional comparison Canadian, Japanese, Korean and US American agen- have been made between the combined models created cies. The ENSEMBLE system can be seen as a web- by the weights calculated in different manner: the based decision support system for real-time exchange BMA-based and the least square fitting with the avera- and evaluation of national long-range dispersion fore- ge and two medians: the median obtained from the casts of nuclear releases with cross-boundary consequ- models’ results of the simulations and the median cal- ences. The created datasets within the ENSEMBLE culated using probability density function resulted from system can be statistically evaluated to generate various the BMA scheme. In general it can be stated that for uncertainty measures of predicted concentrations. Apart emergency response purposes the median model can be from real-time exercises the ENSEMBLE group was considered as a reasonable compromise. also activated to perform simulations both for ETEX-1 and ETEX-2 experiments [3]. For the purpose of the References analysis the results of the models’ simulation as well as [1] F. Girardi et al., (Eds), The ETEX project, EUR Report measurement data were put on a regular geographical 181-43 EN, Luxembourg (1998) [2] S. Galmarini et al., Atmospheric Environment 38 4607 grid of 0.5o· 0.5o resolution and with 3h time step. Made (2004) in 2004, first analysis of the ETEX-1 experiment based [3] S. Potempski et al., Multi-model ensemble analysis of on 16 models’ dataset by the means of the ENSEMBLE the ETEX-2 experiment, submitted to Atmospheric En- system, showed that the median of the distribution of vironment models’ results (“median model”) gave better results than any other single model or average of the
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IMPROVING OFF-SITE EMERGENCY MANAGEMENT: DEMONSTRATION PROJECTS UNDER EURANOS FRAMEWORK S. Potempski,1, 2, S.Galmarini2 1Institute of Atomic Energy 2Institute for Environment and Sustainability, EC JRC, Ispra, Italy The EU integrated project “European approach to ENSEMBLE modelling community and relating to a nuclear and radiological emergency management and specific release case. rehabilitation strategies” (EURANOS) was established The ENSEMBLE system has been perceived by to harmonize European efforts in improvement of off- the participants of the CAT2DEM02 demonstration site emergency in case of nuclear accident anywhere in project as a very useful tool in supporting decision Europe. The MANHAZ centre of the Institute of Ato- makers in case of nuclear emergency [1]. The multi- mic Energy acting as the Technical Support Organisa- model approach is seen as relevant for emergency re- tion for the Centre for Radiation Events of the National sponse because it can assist in producing more scienti- Atomic Energy Agency is also involved in the project. fically justified judgment on the radiological situation In 2007 a main demonstration subproject was entitled during such an event. In particular, verification of na- “ENSEMBLE evaluation of long-range atmospheric tional dispersion calculation results can be easily per- dispersion forecasts from national weather and predic- formed by the means of the ENSEMBLE system. Po- tion services”. ssibility of detailed and objective comparison of diffe- The purpose of all demonstration projects is also to rent models is a great value of the system. The informa- engage National Emergency Centres using RODOS in tion provided by the ENSEMBLE system can be very specific exercises, where they could test both the func- useful for early phase of the nuclear accident, essential- tionality and the usability of RODOS for specific non ly in case of the transboundary issues. NPP issues. The objective of the demonstration therefo- The system is seen as user friendly and easy to re was twofold, to gain the experience in operating and operate. Nevertheless the participants suggested some using RODOS for non NPP events and to provide fe- further improvements. Some of the proposed improve- edback on both the usefulness and the improvements ments are already in the new version of the system, needed within RODOS. which appeared in the meantime. For example, it con- The aim of the mentioned above subproject on op- cerns GIS-like approach for the presentation of the erability of RODOS and ENSEMBLE systems was to results in the system. demonstrate the adequacy of the ENSEMBLE approach Some participants suggested also the need of more and system to support the decision making in the early training before practical use of the system, as the sys- phase of an accident. tem was originally designed for meteorological centres, All the opinions and suggestions presented in the where understanding of the ensemble methodology is institutional reports have been grouped into the follo- higher than in emergency centres. wing categories: The most critical part of the system is related to 1. Relevance of the dissemination of multiple model the ENSEMBLE-RODOS interface. All the participants forecasts for emergency response. would like to have a possibility of calculating doses 2. Adequacy of the ENSEMBLE system for emer- basing on the concentration fields available in the gency management centres. ENSEMBLE system. However, currently this interface 3. User interface, design, functionality. can be treated rather as a premature prototype. Besides 4. Adequacy of the ENSEMBLE-RODOS interface. there are other unsolved elements, related to lack of 5. Other aspects. consistency between both systems: ensemble approach A special session of the ENSEMBLE system was for dealing with uncertainties is not incorporated into organized for the demonstration project CAT2DEM02. the RODOS system by any means. All participating institutes received proper user ID and Additionally some operational aspects should be password to access this session. The session was a fully solved in case of inclusion of the ENSEMBLE system functional version of the ENSEMBLE system where into national emergency plans. the specific dataset for the demonstration were avail- able. By accessing the system each users had the possi- References bility to operate the ENSEMBLE system with the tools [1] B. Tomic et al., EURANOS: Summary Report for using actual datasets as usually produced by the CAT2DEM02, EURANOS(DEM2)-TN(07)-01 (2007)
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SECURITY OF INDUSTRIAL CONTROL SYSTEMS M. Borysiewicz Institute of Atomic Energy Recently, several factors have raised concern about system components, and requirements for the physical the security of industrial control systems (ICS) which environment and protection of the system. The goal of are key components of much of national critical infra- this aspect of analysis and design is to define security structures including the electric power, water and water requirements for subsystems or system components at treatment, oil and gas production and distribution as the lowest possible level while at the same time retain- well as industrial and military manufacturing. First, ing the required level of assurance and security func- there has been a general trend to replace specialized tionality for the integrated system as a whole. The secu- control devices, particularly controllers and communi- rity subsystem includes both the information technol- cations elements, with general purpose computer equ- ogy based components and the non-information tech- ipment and associated data communications techno- nology based elements implemented via policies and logy. Second, many companies have chosen to inter- operating procedures. Particular attention is given to connect certain parts of their process control networks the interaction and dependencies between the security with their corporate intranet once they have introduced subsystem and the overall industrial control system. general-purpose equipment into the process control The System Target of Evaluation (STOE) deals system. with protecting data confidentiality, data integrity and To help industry address these issues, the National system availability without interfering with safety sys- Institute of Standards and Technology (NIST) has initi- tem functions. Data integrity focuses on protecting data ated an industry wide group called the Process Controls flows to and from the controller and the other ICS com- Security Requirements Forum (PCSRF) [1]. The ponents or subsystems. The STOE is also intended to PCSRF is developing its security specifications using protect system availability to assure continuity of op- the Common Criteria (CC). The CC, ISO/IEC 15408 erations. The STOE consists of the security services [2], is a meta-standard of criteria and constructs used to and procedures, both automated and manual, which are develop security specifications in support of the evalua- designed to meet the security objectives defined to tion of products and systems. The specifications define counter threats to the ICS. The recent work [5, 6] pre- and characterize the security problem including as- sents the development of structured methods ICS secu- sumptions about the operational environment, threats rity analysis including STOE framework. that may be encountered and policies that must be en- forced. Also characterized is the intended approach to References eliminate, minimize or monitor defined threats, and [1] Process Control Security Requirements Forum enforce stated policy. (PCSRF) http://www.isd.mel.nist.gov/projects/processcontrol/ The PCSRF has developed the Security Capabili- [2] Common Criteria for Information Technology Security ties Profile (SCP) [3] as a first step towards develop- Evaluation (1999) ment of protection profiles for industrial control sys- [3] Security Capabilities Profile (SCP) (2003) tems. (SPP-ICS) [4]. It is an extension of the ISO/IEC [4] System Protection Profile for Industrial Control Sys- 15408 Common Criteria to support integrated systems. tems (SPP-ICS) Version 0.91 (2004) [5] M.Borysiewicz, J.S.Michalik, Cybersecurity of indu- The SPP-ICS specifies the integrated set of secu- strial control systems, Bezpieczeństwo Pracy, 10 8 rity requirements for industrial control systems. The (2007) integrated set of requirements includes requirements for [6] M. Borysiewicz et al., Methodology of integrated risk operating policies and procedures, requirements for assessment of major accidents and terrorist threats for chemical installations. CIOP-PIB, Warszawa (2006) information technology based system components, requirements for interfaces and interoperability between
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USE OF HPAC PACKAGE FOR RISK SIMULATION IN RELEASE OF DANGEROUS SUBSTANCES IN THE ATMOSPHERE M. Borysiewicz1, J. Dyczewski1, M. A. Borysiewicz2 1Institute of Atomic Energy 2Institute of Electron Technology, Warsaw One of the current objectives for Centre of Excel- The scenario conditions can be set in great detail, lence MANHAZ is acquiring the ability to calculate taking into consideration many factors which may in- scenarios for crisis situation management for chemical fluence the consequences of the release, including the and radiological emergencies, especially in urban areas. description of the CBN agent used (species, quantity, The main tool used for this purpose is the U.S. Defence container type, localisation) and its carrier, the localisa- Threat Reduction Agency’s Hazard Prediction and tion of the event, current and forecast meteorological Assessment Capability (HPAC) code enabling the user conditions, local topology, urban geometry and single to simulate risks arising from releases of dangerous building interior geometry. For the selected scenario substances to the atmosphere. HPAC provides calculated contaminant concentrations and risks as well as predictions of their dispersion in the HPAC enables the calculation of a range of diffe- environment. The MANHAZ implemented the HPAC rent chemical/biological/nuclear (CBN) agent release code and carried out pilot calculations for several loca- scenarios, which include scenarios taking place: tions in Warsaw to test the applications of the code. - in a chemical/nuclear/industrial facility, The report [1] describes the HPAC code possibilities - in an urban environment, and the work methodology and can be treated as a - during transport, documentation for the Polish user of the code. - as a result of using a chemical/radiological weapon, - as a result of intercepting a missile with a CBN References load. [1] M. Borysiewicz, et.al., Report B–48 (2007) (in Polish)
PRESENTATION OF FLUENT PACKAGE CAPABILITIES M. Borysiewicz, Ł. Czerski, H. Wojciechowicz Institute of Atomic Energy The CFD (Computational Fluid Dynamics) pro- over recent years. While many of the simpler dispersion grams allow detailed calculational analysis of fluid models are based on a set of prescribed meteorology to flows in complex environment, eliminating the neces- calculate dispersion, the CFD approach has the ability sity of time-consuming and expensive experimental of coupling the wind field to dispersion processes. This investigations during the design and modernization has distinct advantages when very detailed results are cycle of devices. The CFD programs allow to get the required, such as for the case where the releases occur essential information about flow of liquid (the layout of around buildings and within urban areas. CFD also has velocity field, pressure field), the heat and mass transfer great flexibility as a testbed for turbulence models, including chemical reactions. which has important implications for atmospheric di- spersion problems. The CFD models are used in industries including aerospace, automotive, chemical processing, power The accurate prediction of the spread of dangerous generation, heating, ventilation, air conditioning, bio- substances is important for scenarios that help in pre- medical, oil and gas, marine and many others. From paring for possible attacks, as well as in the analysis ventilation comfort in large buildings to the tiniest scale and damage assessment that follows an event. in micro-pumps and nanotechnology, a wide range of The IAE report [1] includes description of CFD problems can be addressed due to the scalable nature of package FLUENT adapted to cluster of computers in fluid dynamics. Specialized models for combustion, the Centre of Excellence “MANHAZ” enabling parallel reacting flows and radiation, rotating machinery, elec- processing and calculation examples. tronics cooling and many other applications, help provide the insight into equipment and processes requ- References ired to increase production, improve longevity and [1] M. Borysiewicz et al., IAE Report B–53 (2007) decrease waste. (in Polish)
The application of Computational Fluid Dynamics (CFD) to the understanding of urban wind flow and dispersion processes has gained increasing attention
90 ANNUAL REPORT 2007 Nuclear Techniques in Health and Environment Protection Management of Hazards
THE EXPERIMENTAL STUDY OF VOCs REMOVAL FROM EXHAUST GASES USING THE ELECTRON BEAM FROM AN ACCELERATOR A. G. Chmielewski1, A. Ostapczuk1, J. Licki2 1Institute of Nuclear Chemistry and Technology, Warsaw, Poland 2Institute of Atomic Energy Volatile organic compounds (VOCs) are released removal of particulate substance from a sample gas. into atmosphere from various industrial processes. The- After filtration, the sample gas was transported through ir main origins are: mobile sources, organic solvent a heated stainless steel tube to a dry-ice-cooled conden- application, petroleum industry, combustion of fossil sate trap (to separate a condensate) and to a gas adsorp- fuels (industrial and non-industrial), waste treatment tion tubes (two tubes of XAD-2 resin and one tube of and disposal. Emission of VOC to the atmosphere can activated carbon). Gas filters and gas transported line cause stratospheric ozone layer depletion, ground level were kept at the same temperature of 180ºC to avoid photochemical ozone formation and toxic or carcino- condensation. In each run, the sampling flow rate was genic human health effects. VOCs contribute to the of 1l/min and the gas volume sample was about global greenhouse effect. The reduction of VOCs emis- 300 liters. After completion of the sampling the con- sion is of a growing concern of international conven- densate trap and sorbent tubes were hermetically clo- tions as well as EU Directives. The purpose of this sed, wrapped in aluminium foil and shipped to the labo- project was to study the concentration of VOCs emitted ratory in a portable refrigerator. Samples were analyzed from combustion of the light fuel oil Ekoterm-Plus in the following 48h (to prevent degradation) using a (PKN Orlen, Płock) and their removal efficiency using GC/MS system, manufactured by Shimadzu (Japan). the electron beam from an accelerator. The light fuel oil Ekoterm-Plus (Table 1) is commonly used for residen- Very low concentrations of SO (in the range 20- tial heating in the municipal and living sectors in Po- 2 35 ppmv) and NOx (in the range 15-25 ppmv) occurred land. in the flue gas. Table 2 presents the VOCs identified in Table 1. Properties of light fuel oil Ekoterm-Plus. the light oil combustion gases. Property Unit Value Table 2. VOCs identified in the light oil combustion gases. Density at 15ºC kg/m3 830.8 Compounds Concentration Kinematic viscosity at 20ºC cSt 3.88 Subgroup 3 group [µg/Nm ] High heating value MJ/kg 42.6 Sulfur content % wt. 0.04 Aliphatic Alkanes 101 Water content % wt. 0.015 hydrocarbons Alkenes 101 Ash content % wt. 0.002 Aromatic hydrocarbons BTX 101-102 Pour point ºC -30 PAH 2- and 3-ringed 101-102 Flash point C 66 Oxidized aromatic Aromatic acids 101-102 Aromatic alde- 101-102 The study was performed in the laboratory plant hydes [1] at Institute of Nuclear Chemistry and Technology at Hydrocarbons Aromatic alcohols 101-102 Warsaw. The oil was burned by a Jet 4.5 EV burner. Hydrocarbons contain- Thiophenes 100 The obtained flue gas was irradiated in a process vessel ing sulphur Thiazoles 100 (PV) by the electron beam from the ILU-6M accelera- tor. At the inlet PV, the sample gas was extracted for The identified volatile organic compound occurred 3 analysis of flue gas composition by two independent in low concentrations of µg/Nm . Among them in the µ 3 systems. The SO2 and NO/NOx concentrations were higher concentrations of 10-100 g/Nm were detected: continuously determined by a set of two extractive gas aromatic hydrocarbons, oxidized aromatic hydrocar- analyzers The Model 10A/R (chemiluminescence bons and 2- and 3-ring PAHs. The main adverse envi- NO/NOx analyzer) and the Model 40 (pulsed fluores- ronmental impacts of VOCs are connected with the cent SO2 analyzer), manufactured by the Thermo Envi- photochemical ozone formation in the atmosphere. In ronmental Instrument Corporation (USA). the case of this flue gases these effects were insignifi- cant due to the low identified concentration of NOx Organic pollutants occur in flue gas in two phases: which is necessary for these photochemical reactions. particulate phase and gas phase consisting of semivola- The 2- and 3- ring PAHs do not reveal the carcinogenic tile and volatile compounds with boiling points higher effect on humans. Thus the total environmental reactiv- than 100ºC. The project was dedicated to gas phase ity of this flue gas is very low. volatile compounds. Their concentrations were deter- mined by an off-line method. The sample probe was References made from stainless steel and was fitted with heated gas [1] A. G. Chmielewski et al., IAEA-SM-325/124, Vienna filters. Two ceramic coaxial filters were used for the (1992) 91
ANNUAL REPORT 2007 Radioisotope Centre POLATOM
RADIOISOTOPE CENTRE POLATOM K. Małetka, A. Markiewicz, R. Mikołajczak, E. Byszewska-Szpocińska, T. Dziel Institute of Atomic Energy Radioisotope Centre POLATOM, since January - development of technology and implementation of 1st 2007 in the structure of the Institute of Atomic En- isotope generator 188W/188Re production; ergy, is active in the research and development of appli- - manufacturing technologies for carrier free 90Y and cation of radioactive isotopes in science, nuclear medi- carrier-added 177Lu suitable for labeling of cine, industry and environmental protection. radiopharmaceuticals for therapeutic use; - manufacturing methods of 123I-α-methyl-tyrosine The main Research and Development domains of Ra- and 131I-α-methylotyrosine for diagnosis of brain dioisotope Centre are: tumour and its metastasis; - new radiopharmaceuticals showing the affinity to - method of internal electrolysis used for deposition cell receptors for diagnostic purposes and for radio- of 106Ru and 125I layers on metallic surface for immunotherapy; manufacture of active cores of sealed sources; - radiopharmaceuticals containing peptides, proteins - manufacturing technology of 125I sealed sources in and monoclonal antibodies for imaging of inflam- the form of miniature 125I seeds for brachytherapy matory sites; of intrabrain, prostate and eyeball tumours; - methods of elements separation and their applica- - development of technologies for manufacture of tion for production of radionuclides of high specific peptide based kits for 99mTc-labelling for use in on- activity, including radionuclides generators; cological diagnostics; - new types of miniature sealed sources for - development of absolute measurement methods of brachytherapy; radionuclides’ activity with liquid scintillation - new types of sealed radiation sources for industrial counters (LSC). applications; - development of preparation methods for manufac- The Centre has developed very good communica- turing radiopharmaceuticals, radiochemicals and tion links with the leading clinical centers and nuclear medical materials; medicine departments and Institutes in Poland involved - studies on the analytical techniques for quality in radiopharmaceutical and radiobiological develop- assurance of medical products; ments as well as with many international research insti- - development of methods for radiation activity tutions. This cooperation is supported by scientific and measurement and determination of radionuclides in applied grants provided by Ministry of Education and radioactive materials; Science. The Centre actively contributes to the research - new reference materials for ionizing radiation projects carried out by the international organizations measurement. and programs: - International Atomic Energy Agency (IAEA); Since 1999 RC POLATOM has been depositary of - European cooperation program in the field of scien- national standard unit of radionuclide activity to which tific and technical research COST; the parameters of other reference materials are related - EUREKA Initiative. through a chain of comparisons. The national standard is supervised by the President of The Central Office of Since 2005 RC POLATOM is a member of Con- Measures (GUM). sortium and takes part in the Network of Excellence Diagnostic Molecular Imaging (DiMI), in the frame- In 2007 several issues have been successfully work of sixth program, FP6 of the European Commu- accomplished: nity.
95 Radioisotope Centre POLATOM ANNUAL REPORT 2007
ELECTROCHEMICAL PROCESSES OF FIXING RADIONUCLIDES APPLIED IN SEALED SOURCES FOR BRACHYTHERAPY I. Cieszykowska, M. Mielcarski Institute of Atomic Energy One of the methods frequently used in oncology is Table 1. The leachability of 125I wire sources. radiotherapy. In particular, dynamic development of Description of Activity of source Activity leached out brachytherapy is observed recently [1]. In this treatment source [MBq] sealed radiation sources of 106Ru, 125I and in some cases [kBq]/[%] also 192Ir, 90Sr or 103Pd are used. The most important Protected Ag 35.43* 15.3*/0.04 task for manufacturing such sources is fixing of the wire radionuclides to the source cores [2-4]. Unprotected 40.00* 43.1*/0.1 Ag wire Our results on application of electrochemical meth- * Uncertainty of activity determination ± 5% ods, in particular of the internal electrolysis [5], to the 125 source fabrication are presented in [6]. These methods The distribution of I along the wire is fairly appeared to be effective for fixing both metallic (106Ru, good. However, a wide maximum is observed for the palladium) and non-metallic (125I) deposits as well as central part of the wire (Fig. 1). simultaneous co-deposition of metal with non-metal e.g. 125I with palladium on a silver substrate. As a result of the investigations performed, opti- mum conditions for fixing 106Ru on a silver base by means of an internal electrolysis were determined. This method was implemented in practice for manufacturing ophthalmic applicators used in eye cancers treatment. These methods of manufacturing of the active cores of the 125I seed-type sources are discussed compara- tively. These were a fixing of 125I on the silver surface, a fixing of 125I on the silver plated with palladium and a codeposition of 125I with palladium on silver. After electrolysis, lasting 24 h, 80% of 106Ru con- tained in an electrolyte solution was withdrawn and deposited on the silver cathode. The deposits thus ob- Fig. 1. Activity distribution along the unprotected silver wire. tained were 2 µm thick, metallic and lustrous, adhering well to the silver backing, showing no tendency to chip- The developed methods of fixing of 106Ru and ping or cracking. 125I on a silver base enabled manufacturing of ophthal- The high quality of the deposit obtained with a car- mic applicators with a monolitic active core of the activ- rier-free 125I reduced contamination problems and made ity required for therapeutic applications (13-27 MBq for this choice more reasonable from a practical point of 106Ru and 1.85-9.25 GBq for 125I). view. As a result of the process lasting 70-90 h, 97-98% of 125I contained in the electrolyte solution was with- References drawn. [1] J. Sienkiewicz et al., Wiad. Lek., 55 569 (2002) For each technique applied, the yield and the uni- [2] C. Mathew et al., App. Radiat. Isot. 57 359(2002) formity of deposition as well as the leachability were [3] Ch. Zhang et al., App. Radiat. Isot. 57 309 (2002) [4] R. Monolkar et al., App. Radiat. Isot. 59 145 (2003) determined. The leachability of 125I fixed to the unpro- [5] G. Milazzo, Electrochemistry, Elsevier, Amsterdam tected silver bars does not exceed 0.1% and is even (1963) lower for protected bars (Table 1). [6] I. Cieszykowska. PhD Diss., Institute of Nuclear Chem- Nevertheless, in the case of an unprotected source istry and Technology, Warsaw (2007) [7] R. Kuznetsovert et al., IAEA-TECDOC-1512 (2006) the leachability was still lower than others’ results [7].
96 ANNUAL REPORT 2007 Radioisotope Centre POLATOM
THE DEVELOPMENT OF A PREPARATION METHOD OF ALBUMIN MICROSPHERES AS POTENTIAL RADIONUCLIDE CARRIERS FOR DIAGNOSTIC AND THERAPEUTIC USE J. Pijarowska, A. Jaroń, E. Iller Institute of Atomic Energy Human serum albumin microspheres (HAM) of various size have been widely used for clinical nuclear medicine as carriers for radioactive diagnostic and therapeutic molecules since 1969 [1, 2]. Their widest application was found in scanning of lungs in a diagno- sis of pulmonary embolism, pulmonary infarction and other lung disorders.
The purpose of this study was to develop a prepara- Fig.1. Optical micrographs of HAM in average size range of tion method of batches of albumin microspheres with 10-32 m taken at two different magnifications (×200 reproducible statistics, reproducible physical and bio- and ×400). logical parameters which can be labeled with a variety of radionuclides and will comply with the requirements The percentage frequency of microspheres particles for API (Active Pharmaceuticals Ingredient). In general, in particular the size range was determined by weight the preparation of HAM consists in dispersion of a hu- analysis (Table 1). man serum albumin (HSA) solution in a suitable me- Table 1. Particle size ranges of albumin microspheres. dium and heat stabilization of spherical particles. In the present study HAM were prepared by the Frequency of HAM[%] emulsification and heat stabilization technique de- Batch No. Size range [ m] scribed previously [3,4], with minor modifications. The <10 10-32 32-50 50-100 >100 processing parameters of homogenization (speed and 1 0.9 86.9 7.2 2.3 2.7 time), oil phase (volume, emulsifier and denaturating 2 0.4 84.1 11.8 2.2 1.5 factor concentration), water phase (volume and HSA 3 0.3 81.8 13.9 2.1 1.9 concentration) and protein denaturation heat Average 0.5 84.3 11.0 2.2 2.0 (temperature and time) were selected in an experimental way. The optimized method consisted of adding a HSA The average production yield of the desired HAM solution containing SDS to liquid paraffin containing size range of 10-32 m amounts to 84% and the mean SDS and Tween 80 and stirring the mixture with me- size of particles was approximately 15 m. Optical chanical stirrer to obtain water/oil emulsion. This emul- micrographs show microspheres as very regular spheri- sion was then heated to allow the formation and solidi- cal forms with quite smooth surfaces and slight scatter fication of microspheres. The supernatant oil was re- of size in the dominant range (Fig. 1). moved by decantation and microspheres were washed In continuation of this project the albumin with diethyl ether. Then particles were dried in vacuum microspheres will be labeled with 99mTc and β-emitter and later sieved. radionuclides. For the HAM labeling with 99mTc the reduction of technetium valency is necessary. As reduc- Ten batches of microspheres ranging in a diameter tor SnCl ×2H O will be used and the development of from 10 to 32 m were prepared by the described 2 2 a method of attaching technetium to microspheres will method. The particle size analysis was performed by an be required. The prepared radiopharmaceuticals will be optical microscopy using a light microscope equipped then tested for their in vivo stability and biodistribution. with an ocular micrometer and a light camera (Fig. 1).
The microspheres were sized and photographed in a References normal saline containing Tween 80 to prevent [1] B.A. Rhodes et al., Radiology 92 1453 (1969) aggregation. The particles in each prepared batch were [2] G. Wunderlich et al., Appl. Radiat. Isot., 52 63 (2000) [3] R.L. Evans, US Patent Office 663.687, (16.05.1972) measured using a calibrated ocular micrometer and [4] B. Łucka et al., Report 174/OpiDI (1981) a special computer program.
97 Radioisotope Centre POLATOM ANNUAL REPORT 2007
NEW DIAGNOSTIC KIT HYNIC-IGG LABELLED WITH TECHNETIUM-99m FOR INFLAMMATION IMAGING E. Byszewska-Szpocińska1, U. Karczmarczyk2, J. Michalik1, M. Górska-Chrząstek3, J. Kapuściński4, J. Kuśmierek4 1Institute of Atomic Energy 2National Medicines Institute, Warsaw, Poland 3Nuclear Medicine Department, Medical University, Łódź, Poland 4Department of Quality Control and Radiological Protection, Medical University, Łódź, Poland
Scintigraphic detection of infection and inflamma- 2.5 tion enables the determination of both location and 3 h number of infectious and inflammatory foci throughout 2 24 h the body. Since scintigraphic images are based on func- 1.5 tional tissue changes, infectious and inflammatory foci can be visualized in their early phases, when anatomical 1 changes are not yet apparent. IgG accumulates in infec- % % ID/g organ tious foci by a non specific extravasation due the locally 0.5 enhanced vascular permeability. The 99mTc – labelled preparations have known ideal radiation characteristics. 0 Gammaglobulin can be labelled by a direct or indirect liver kidney non inflammed treated muscle method of radiotracer incorporation in the protein mole- muscle cule. The direct method of labelling is connected with organ changes in the secondary and tertiary structure of IgG molecule. The indirect labelling method using bifunc- Fig. 1. The time- dependant organ biodistribution of 99mTc- tional chelate hydrazinonicotinamide (HYNIC) pre- HYNIC-IgG in rat with an inflamed thigh muscle after serves the structure and biological activity of the protein 3 and 24 h p.i.(% administration dose per gram of an [1-3]. organ).
The HYNIC-IgG conjugate with a HYNIC:IgG 2:1 Scintigraphy with 99mTc-HYNIC-IgG was perfor- molar ratio lyophilized in citrate buffer pH 5.5 stable in º med in patients with clinically osteomielitis or septic 4-8 C for 6 month was obtained. The method of techne- arthritis. The relative uptake of the radiopharmaceutical tium-99m labeling of this conjugate was investigated in in inflammation spots comparing to the background was the presence of SnCl2 as a reductor and tricine as a coli- very high (Fig. 2). gand. Finally, the formulation of the dry kit for the HYNIC-IgG labelling with technetium-99m was as follows: vial I – 2mg HYNIC-IgG in 200 l, citrate buffer pH 5,5; vial II – 11.7 g SnCl2×2H2O) + 200 g tricine in 200 l PBS. The radiochemical purity of the tracer 99mTc- HYNIC-IgG was ≥95% (determined by instant thin- layer chromatography analysis - ITLC). The obtained tracer contained ≤16% of 99mTc-HYNIC-IgG aggregates (HPLC using BioSep-SEC-S-2000 PEEK column with isocratic elution analysis). 99mTc-HYNIC-IgG was sta- ble in human serum in vitro during 4 h incubation at Fig. 2. SPECT/CT scintigraphy with 99mTc-HYNIC-IgG, ac- 37ºC. quisition 24 h after the tracer administration indicating an inflammatory process in the right hip. In the animal biodistribution studies, 24 h post in- 99m jection (p.i) of Tc-HYNIC-IgG a high specific radio- The obtained new human immunoglobulin deriva- activity accumulation in the inflamed thigh muscle tive IgG-HYNIC labelled with 99mTc by the indirect compared with a non treated muscle was observed method with a high radiochemical purity can be very (Fig. 1). helpful in the assessment of localization and of the ex- tension of the inflammatory process.
References [1] A. Roland et al., Eur. J. Nucl. Med. 23 414 (1996) [2] J. Huub et al., Nucl. Med. Biology 27 599 (2000) [3] M. Abrams et al., J. Nucl. Med. 31 2022 (1990)
98 ANNUAL REPORT 2007 Radioisotope Centre POLATOM
THE DEVELOPMENT OF A 188W/188Re GENERATOR FOR THE THERAPEUTIC USE R. Mikołajczak, D. Pawlak, M. Zuchlińska, M. Konior, J.L. Parus Institute of Atomic Energy 188Re is a radioisotope of a high therapeutic poten- because the 188W mother radionuclide has the half-life tial for nuclear medicine, which belongs to the beta – of 69 days. gamma emitters group (maximal energy of beta radia- In our testing procedure the performance of the tion is 2.11 MeV, energy of gamma rays is 155 keV). generator has been evaluated for 6 months period. Ac- With beta particles penetration in soft tissues of about cording to this procedure several generators were fabri- 8 mm the cancer tissues can be destroyed, while the cated with a nominal activity of 188Re in the range from emission of gamma radiation permits imaging to locate 4 to 15 GBq at the calibration date. The activities of the accumulation. Studies include the clinical use of 188Re 188Re obtained from a generator were up to 500 mCi at complexes with HEDP as an effective pain palliation the calibration date and over 90% of activity was eluted agent in painful bone metastases and with DMSA for in first 4 ml of effluent (radioactive concentration of cancer treatment. 188Re complexes with peptides and 188Re from 15 to 120 mCi/ml), hence no post-elution monoclonal antibodies and their use in therapy against concentrating was needed. The radiochemical purity cancer are also in progress. Sterile and pyrogen-free was above 98.0% and radionuclidic purity >99.9% with solutions of 188Re agents have been used in brachyther- respect to gamma impurities. 188W leakage was <0.5%, apy of coronary vessels to prevent restenosis [1-5]. whereas chemical purity testing showed Al < 10 ppm. Because of the short half-life of 188Re, supplying The eluates were sterile and free of bacterial endotoxi- the medicament to remote customers can create a logis- nes. The quality of the 188Re solution has been tested in tic problem, which can be solved by delivering labelling of bombesin analogue [8]. Described genera- 188W/188Re generators as a source of 188Re [6,7]. We tors can be used in the clinics for routine applications as have used a generator column and lead shielding used in well as in research laboratories. our standard 99Mo/99mTc generator (fission produced 99Mo) to fabricate 188W/188Re generators. Aluminium 100% oxide (Alumina A, ICN, MP Biomedicals) was used as a solid support. Before loading 188W, the support was 80% activated by subsequent washing with the following 60% solutions: 5 ml 0,9% NaCl solution acidified to pH=3, 5 ml 32% HCl and 20 ml 0,9% NaCl solution, 40%
pH=3, all at a flow-rate 10 ml/min, to obtain an effluent yield Relative of pH=3. 20% The 188W (RIAR, Russia) with a specific activity 0% between 27 GBq/g W and 133 GBq/g W, was dissolved, 1 2 3 4 Number of fraction before loading on the column, in 0.5M NaOCl (0.5 ml NaOCl per 1 g of W), 80% CH COOH (1 ml 3 Fig. 1. The yields of 188Re elution in collected 4 ml fractions CH3COOH per 1 g of W) and 32% HCl, in order to over 10 consecutive elutions . lower the pH of the solution to 2.5, to obtain tungstenic 188 188 acid. The W solution (as H2 WO4) was then slowly We acknowledge the support of the IAEA coordinated loaded on the column using a peristaltic pump (flow rate research project No 12880. 0.1 ml/min). The chemical quantity of W loaded on the column was between 40 to 80 mg/g of alumina. The References 188Re was eluted from the generator with 0.9% acidified [1] K. Liepe et al., Am J Hosp Palliat Car. 22 457 (2005) saline. [2] S. Lee et al., Am Heart J. 158 (2006) [3] B. Lambert et al., Eur J Nucl Med Mol Imaging. 33 344 The elution profile of the generator is presented in (2006) Fig. 1 where average values of generator yields obtained [4] S. J.Wang et al., Nucl Med Biol. 28 727 (2001) in 10 consecutive elutions (over the period of 4 weeks) [5] G. Ferro-Flores et al., Nucl Med Biol. 26 57 (1999) are shown. More than 95% of 188Re activity were accu- [6] F .F. Knapp et al., Anticancer Res. 17 1783 (1997) [7] F. F. Knapp et al., Anticancer Res. 17 1803 (1997) mulated at first and second fractions. The 188W/188Re 188 [8] E.Koumarianou et al., J Label Compd Radiopharm. 50 equilibrium is reached in about 72 hrs, however, Re S241 (2007) can be milked from the generator more often with a satisfactory yield. According to the literature [6, 7] 188W/188Re generators can be used for above 6 months,
99 Radioisotope Centre POLATOM ANNUAL REPORT 2007
THE INTERCOMPARISON OF 99mTc AND 131I MEASUREMENTS BY RADIONUCLIDES CALIBRATORS IN POLISH HOSPITALS 2007 R. Broda, T. Dziel, A. Muklanowicz, A. Listkowska, Ł. Pieńkowski, A. Patocka, E. Kołakowska Institute of Atomic Energy
Basing on the experience and publications of for- The result given by each participant (Aparticipant) and eign metrological laboratories [1, 2], the Laboratory of the result obtained in the LRS (ALRS) was recalculated Radioactivity Standards (LRS) has organized in Polish for the same reference date and the ratio hospitals an intercomparison of activity measurements S = A / A of 99mTc and 131I. Both radionuclides are generally used participant LRS was determined. The half-life of (6.0067±0.0010) h of for diagnostics and therapy. Organization of the inter- 99m 131 comparison has been financed in 2007 by the National Tc and of (8.0233±0.0019) d of I was adopted [3]. Atomic Energy Agency and supported by the Polish Not all of participants have delivered an estimated Society of Nuclear Medicine. uncertainty of measurement, and then it was impossible From among 58 Polish hospitals invited, 37 have to evaluate their measurement results using the En crite- participated in the intercomparison. Each hospital was rion [4]. The statistical criterion called normalized stan- identified by a confidential participant number. dard deviation, D A − A The goal of the intercomparison was to obtain an D = participant LRS information on the accuracy of activity measurements in σ LRS 3 Polish hospitals in relation to the National Standard Unit of Radionuclide Activity and to increase the efficacy of has been used. The ALRS was adopted as the reference diagnostics, therapy and security of patients. All radio- value. The parameter D was used to classify the meas- active sources for measurements were manufactured in urement results according to the specified limits [5]: the RC POLATOM and delivered to participants suc- |D| ≤ 2 - good (within all limits), cessively during 4 months. 2 < |D| < 3 - acceptable (within the warning limits), ≤ | | Each participant received about 4 ml of 99mTc elu- 3 D - non-acceptable (out of control). 131 ate in a glass vacuum-vial used for elution, and two I The measurement result which differ no more than capsules, low- and high-active, in separate glass vials. ±5% from the reference ALRS value was assumed to be Sources were standardized in relation to the National suitable for hospitals purposes [6]. Then σLRS = π Standard using a measurement system with the 4 ioni- 0.044·ALRS was adopted instead of σLRS values given σ zation chamber. The extended uncertainty of LRS = above and, as a consequence, the warning limits of 131 σ 99m ±1.5 % for I and of LRS = ±3.0 % for Tc with the ±7.6% for acceptable results were obtained. extension parameter k = 2 has been evaluated. An exact measurement time has been noted. Participants perfor- Good and acceptable results composed jointly of 75%, 69.2% and 82% for all measurement results in the case med measurements by their own radionuclide calibra- of 99mTc eluate, 131I capsules for diagnostics and 131I tors and sent results to the LRS. Data obtained from 37 capsules for therapy, respectively (Table. 1). From 118 hospitals participating in the intercomparison have results received from participants, 23 (19.5%) were non- shown a big variety of radionuclide calibrators used - 43 acceptable. calibrators of 22 types from 12 various manufacturers.
Table. 1. Classification of the participant results of 99mTc and 131I measurement as good, acceptable and non-acceptable, accor- ding to the limits specified by the D criterion. The limits of participant to LRS result ratio, S, are also given.
Non-acceptable Acceptable Good Acceptable Non-acceptable results results results results results D ≤ -3 -3 < D < -2 -2 ≤ D ≤ 2 2 < D < 3 3 ≤ D S ≤ 0.924 0.924 < S < 0,95 0.95 ≤ S ≤ 1.05 1.05 < S < 1.076 1.076 ≤ S 99mTc 17.5 % 7.5 % 62.5 % 5.0 % 7.5 % 131I for diagnostics 12.8 % 0.0 % 64.1 % 5.1 % 17.9 % 131I for therapy 7.7 % 2.6 % 64.1 % 15.4 % 10.2 %
References [4] ISO/IEC Guide 43-1 (1997) [1] D. MacMahon, et al., NPL Report DQL-RN 018, United [5] N. G. Natrella, Experimental statistics, NBS Handbook Kingdom (2006) 91 3 (1963) [2] A. Iwahara, et al., Appl. Radiat. Isot. 56, 361 (2002) [6] R. Gadd, et al., 93 NPL (2006) [3] Table de Radionucleides, BNM – LNHB/CEA, France (2004)
100 ANNUAL REPORT 2007 Radioisotope Centre POLATOM
ON PHOTON STATISTICS IN THE LS-COUNTER R. Broda Institute of Atomic Energy The method of radionuclide standardization by the quite well (Fig. 1), thus justifying its use for estimating TDCR technique is based on the statistical Poisson the efficiency of low energy emitters.. model of the phenomena occurring when an ionizing particle interacts with the liquid scintillator (LS) [1]. The whole process can be described by binomial statis- tics as a result of a cascade of binomial processes. As the global probability of the whole process is low and the number of emitted photons in the case of high- energy emitters is large, the process can be approxi- mated by a Poisson distribution for practical purposes. However, for the low-energy emitters 3H or 55Fe, the Poisson model failed [2, 3] yielding too high counting efficiency. Satisfactory results of standardizations have been obtained using the negative binomial (Polya) model. Evidently the model needs to include an effect that reduces the number of emitted photons. This could Fig. 1. Approximation of the global distribution for the num- ber of photons, n, collected by photomultipliers from a be result of an optical phenomena occurring when the LS-vial (dashed line) obtained by summing of the three scintillation light is emitted from a LS-vial. Cassette and binomial distribution a), b) and c) related to the differ- Vatin [4] have pointed out that the probability of photon ent layers of scintillator. emission from the LS-vial depends on the emission location and that the global statistics of light emission The energy conversion factor for the liquid scintil- has a larger variance than the Poisson law. lator obtained when determining the 55Fe activity using the Polya model [3], enabled an estimation of the Probabilities of successive elementary processes scintillation efficiency for 14C close to the experimental leading to the fluorescence of a liquid scintillator (ioni- value. This gave further evidence of the correctness of zation along the particle track, quenching of primary the Polya model in the case of the 55Fe measurement. excitation, energy transfer to the solvent, ionization or excitation of π-electrons, internal conversion to the S1 state or quenching, recombination of ions to the S3 or References S1 states, energy transfer to the solute, fluorescence, [1] R. Broda et al., Appl. Radiat. Isot., 39 (2) 159 (1988) internal conversion or quenching in the solute) were [2] R. Broda, K. Pochwalski, in: J. E. Noakes, F. Schö described using existing data [5 - 12]. hofer, H. A. Polach, (Eds.), Liquid Scintillation Spec- trometry 1992, RADIOCARBON, The University of The low-energy emitters 3H or 55Fe of an average Arizona, Tucson, AZ, 255 (1993) energy of interacting particles of 5.7 keV, transfer about [3] R. Broda, A. Jęczmieniowski, Appl. Radiat. Isot., 60 453 (2004) 10% of the energy to the π-electrons and create about 20 [4] P. Cassette, R. Vatin, Nucl. Instr. Meth. Phys. Res. photons per disintegration in fine. Using the evaluated A312 95 (1992) number of photons and the light emission efficiency, [5] R. Cooper, J. K. Thomas, J. Chem. Phys. 48 (11), 5097 ε, versus the radius, R, of the emission point in a vial (1968) [4], the global distribution of light collection by pho- [6] I. B. Berlman, J. Chem. Phys. 33 (2) 598 (1961) tomultipliers of a TDCR detector could be evaluated [7] J. B. Birks, in: D. L. Horrocks, C. T. Peng, (Ed.), Orga- nic scintillators and liquid scintillation counting, Acad. and compared with the Polya distribution. To simplify Press, New York, (1971) the calculations, only three binomial distributions for [8] J. B. Birks, The theory and practice of scintillation the number of photons, n, collected by photomultipliers counting, Pergamon Press Ltd., Oxford, (1964) were used. Distributions were calculated for three cylin- [9] D. L. Horrocks, J. Chem. Phys. 52 1566 (1970) drical layers of scintillator of radius a) R ≤ 0.6, b) 0.6 < [10] D. L. Horrocks, Applications of liquid scintillation R ≤ 0.8 and c) 0.8 < R ≤ 1.0, and summed with the layer counting, Acad. Press, New York, (1974) [11] C. W. Lawson, F. Hirayama, S. Lipsky, J. Chem. Phys. volume weighting factor u = 0.36, 0.28 and 0.36, re- 51, 1590 (1969) spectively. The sum-distribution, which approximated [12] A. Weinreb, in: D. L. Horrocks, C. T. Peng, (Ed.), global distribution of light collection, the binomial, the Organic scintillators and liquid scintillation counting. Poisson and the Polya distribution were calculated for Acad. Press, New York (1971) the expected number n ≈ 2.6 of collected photons. The Polya distribution fits the global distribution of photons
101 Radioisotope Centre POLATOM ANNUAL REPORT 2007
SYNTHESIS AND TESTING OF GEL METAL-OXIDE COMPOSITES AS FILLING MATERIALS FOR W-188/Re-188 GENERATOR COLUMNS E. Iller1, H. Polkowska-Motrenko2, D. Wawszczak2, M. Konior1 1Institute of Atomic Energy 2Institute of Nuclear Chemistry and Technology, Warsaw, Poland
Rhenium has recently showed up as a useful radio- Samples containing WO3-ZrO2-SiO2 did not reveal isotope in variety of clinical trials. satisfactory elution profiles.
At present the carrier–free Re-188 is obtained from W-188/Re-188 generators in which the tungsten-188 in WO3 : ZrO2 = 1 : 2 form of a sodium tungstenate W-188 solution is ad- * T=800°C ° sorbed on the alumina filling of a generator column. °° * ° ° * A new approach to preparation of chromatographic co- ° ° * * ° ° ° ° ° lumn packing of tungsten-188/rhenium generators is an ° * application of nanocomposites obtained by means of the T=650°C sol-gel technique [1-3]. A specific method for the syn- thesis of these materials was elaborated at INCT War- saw Poland. The initial stage of the process is prepara- * * * + tion of the ascorbate- NH4 - tungsten, next the sepa- T=500°C (sample SP)
Intensity rately prepared zirconyl or/and silicon sols are added gradually to the reaction mixture. After a gelation step, gels are thermally treated at temperatures indicated by a thermal analysis (500, 650, 800oC). This way the T=500°C synthesis of nanocomposites containing TiO2-WO3,
ZrO2-WO3, ZrO2-SiO2-WO3 at different ratios of oxides was carried out.
The several methods have been used for the deter- 10 20 30 40 50 60 70 80 90 2θ° mination of their structures and chemical purity.
(∗) The neutron activation analysis and spectrometry Tetragonal ZrO2 [88-1007] were applied for the determination of radionuclidic purity of components (o) Monoclinic WO [71-2141] 3 Intensity The X-ray diffraction analysis and the neutron scat- tering analysis (wide and small angles) allowed for 10 20 30 40 50 60 70 80 90 a determination of their crystal structure [4]. 2θ° The samples were analyzed by XRD using a Ri- gaku Miniflex diffractometer with Cu-Kα radiation Fig. 1. The X-ray diffraction analysis of WO3- ZrO2 (1:2) (tube voltage 30kV and tube current 15mA) and scan- nanocomposites after different temperature treatment. ning range from 2θ=3° to 2θ=90° (step 0.02° and rate 2°/min). The raw data were submitted to the smoothing process by the Savitzky method; the background elimi- The work was supported by the research grant No nation process by the Sonnevelt method and a Kα2 3 TO9B 042 29 of the Polish Ministry of Science and elimination process. Education Next the elution profile of generator column packed on gels samples activated in a nuclear reactor References have been studied using 0,9% NaCl solution as an elu- [1] M.S. Dadachov et al., Applied Radiation and Isotope ent. The best results of elution (profile and eluent pu- 57 641 (2002) [2] M.S. Dadachov, R.M.Lambrecht, J. Radioanal. Nucl. rity) appeared in the case of filling a chromatographic Chem. Letters 200 211 (1995) column with WO3-ZrO2 materials; in which the oxides [3] M.S. Dadachov et al., J. Radioanal. Nucl. Chem. Letters molar ratio was 1:2 and a calcination temperature of 188 267 (1994) o 500 C and WO3-TiO2 with molecular ratio 1:2 and [4] J.J. Milczarek et al,. IAE Report 38-B (2007) a calcination temperature of 650oC. The structural analysis of both composites allowed for theirs classification as amorphous materials.
102 ANNUAL REPORT 2007 Radioisotope Centre POLATOM
DEVELOPMENT OF RADIONUCLIDES STANDARDIZATION METHODS BY MEANS OF A LIQUID SCINTILLATORS TECHNIQUE USING MONTE CARLO CALCULATIONS T. Dziel, R. Broda Institute of Atomic Energy The probabilities of interaction of photons in two The main calculations were performed over the different liquid scintillators (toluene and widely used photon energy range 5 – 1000 keV. For each energy commercial cocktail Ultima Gold) were calculated as value and geometry at least 2·106 initial particles were a function of energy for two different geometries (stan- simulated and the radiation source was assumed to be dard 20 ml LS glass vial and LS cocktail volumes of 10 uniformly distributed throughout the LS cocktail. The and 15 ml) using the Monte Carlo code PENELOPE [1]. calculated probabilities of photon interaction for differ- ent liquid scintillators are comparable (Fig. 2). The used geometries were described by coaxial cylinders (Fig. 1). The vial was surrounded by a simpli- fied counting chamber structure. In order to confirm a validity of our procedure, the results were compared to the results of the calculated absorbed spectra of the 835 keV photons of 54Mn organ- ized by the Liquid Scintillators working group of the International Committee for Radionuclide Metrology in 2004 [2]. The calculated interaction probability values and characteristics of the shape of the resulted spectra, namely, the ratios: the peak-to-valley, the peak-to-valley of the main Compton spectrum and the amplitude of the multiple Compton peak to the amplitude of the main Compton peak were similar in both simulations. Fig. 2. Dependence of the photon interaction probability on the energy. It was observed that in high energy range there was no significant difference between the used scintillators. For energies below 100 keV the difference did not ex- ceed 12%. Lower interaction probabilities in the case of toluene result from the alternate composition of this cocktail having lower amounts of elements with high atomic number (S, P or Na). Difference between 10 and 15 ml of Ultima Gold can be neglected. Table 1. Atomic composition of the scintillators. C H N O P S Na
UG 16,81 24,54 0,04 1,52 0,11 0,02 0,02
Tol 7 8 - - - - -
Results of this work, including calculated spectra of deposited energy in a liquid scintillator for a different energy, will be used in a primary standardization of radioactive solutions by the triple-to-double coincidence (TDCR) method in the Laboratory of Radioactivity Standards in RC POLATOM.
References Fig. 1. Geometry of LS vial used in the Monte Carlo calcula- [1] F. Salvat et al., PENELOPE-2006 Workshop Proce- tions. All dimensions are given in cm. edings, Barcelona, Spain, 4-7 July (2006) [2] P. Casette et al., Appl. Rad. Isot. 64 1471 (2006)
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1. Andrzejewski K., Kulikowska T., Marcinkowska Z., Pytel K.: Computational model of MARIA reactor based on Rebus code. Raport IAE-129/A, Institute of Atomic Energy, Świerk, Poland (2007). 2. Balzarini J., Orzeszko B., Maurin J. K., Orzeszko A.: Synthesis and anti-HIV studies of 2-adamantyl- substituted thiazolidin-4-ones. Eur. J. Med. Chem., 42, 993 (2007). 3. Bilski P., Blomgren J., Espodito A., D’Errico F., Fehrenbacher G., Fernàndez F., Fuchs A., Golnik N., Lacoste V., Leuschner A., Sandi S., Silari M., Spurny F., Wiegel B., Wright P.: The problems associated with the monitoring of complex workplace radiation fields at European high-energy accelerators and thermonuclear fusion facilities. Radiat. Prot. Dosim., 126, 1-4, 491 (2007). 4. Blomgren J., Linndborg L., Golnik N., Jones D., Schuhmacher H., Spurny F., Stenerlöw B.: Progress in dosimetry of neutron and light nuclei. Radiat. Prot. Dosim., 126, 1-4, 1 (2007). 5. Borysiewicz M., Michalik J.: Cyber security of industrial control systems. Bezp. Pracy-Nauka i Praktyka CIOP-PIB, 10, 8 (2007), in Polish. 6. Chmielewski A.G., Licki J.: Application of electron beam for purification of exhaust gases from industrial combustion process. Polish J. Environ. Stud., 16, 3B, 49 (2007). 7. Chwaszczewski S., Kilim S., Mądry M.: Thorium in nuclear energy. Polityka Energetyczna 10, Spec. Issue 2, 97 (2007), in Polish. 8. Czachor A.: Shell model of the Big Bang in special-relativity framework. Acta Phys. Pol., B, 38, 2673 (2007). 9. Czepczyński R, Parisella M.G., Kosowicz J., Mikołajczak R., Ziemnicka K., Gryczyńska M., Sowiński J., Signore A.: Somatostatin receptor scintigraphy using 99mTc-EDDA/HYNIC-TOC in patients with modullary thyroid carcinoma. Eur. J. Nucl. Med. Mol. Imaging, 34, 1635 (2007). 10. Dąbrowski L., Andreev A., Gregoriev M.: Carbon diffusion in α-iron: evidence for quantum mechanical tunneling. Metall. Mat. Trans. 37A, 7, 2079 (2006). 11. Dreda M., Chmielewski A. G., Licki J.: Sulphur isotope compositions of components of coal and S-isotope fraction Turing its combustion and flue gas desulphurization. Isot. Environ. Health Stud., 43, 1, 57 (2007). 12. Gołąb A.: Report on operation of nuclear research reactor MARIA in 2006. PTJ, 50, 1 (2007). 13. Golnik N., Zielczyński M., Bulski W., Tulik P., Pałko T.: Measurements of the neutron dose near a 15 MV medical linear accelerator. Radiat. Prot. Dosim., 126, 1-4, 619 (2007). 14. Golnik N., Zielczyński M., Gryziński M.A., Tulik P.: Recombination processes in high-pressure ionization chambers irradiated with low-LET radiation. Nucl. Instrum. Methods Phys. Res. Sect. A, 580, 25 (2007). 15. Golubok D. S., Didyk A. Y., Hofman A.: Radiation damage calculation for IBR-2 neutron irradiated amorphous Fe77Ni2Si14B7 alloy. Fizika i Chimia Obrabotki Materiałov, 6, 5 (2007), in Russian.
16. Górski L., Pawłowski A.: Studies on Al203 – ZrO2 coatings structure before and after thermal treatment. Solid State Phen., 130, 297 (2007). 17. Gryziński M. A., Golnik N., Tulik P., Zielczyński M.: Initial recombination of ions in ionization chambers filled with hydrocarbon gases. Nukleonika, 52, 7 (2007). 18. Gryziński M. A., Golnik N., Tulik P., Zielczyński M.: Ionization chamber containing boron as a neutron detector in medical accelerator fields. Radiat. Prot. Dosim., 126, 1-4, 274 (2007). 19. Gryziński M.A., Tulik P., Zielczyński M.: Studies of the ionisation chambers containing boron as neutron detectors in mixed radiation fields. Polish J. Med. Phys. Biomed. Eng. 13, 2, 79 (2007). 20. Hubalewska-Dydejczyk A., Fross-Baron K., Golkowski F., Sowa-Staszczak A., Mikołajczak R,. Huszno B.: 99mTc-EDDA/HYNIC-Octreotate in detection of a typical bronchial carcinoid. Exp. Clin. Endocrinol Diabetes; 115, 47, (2007).
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21. Hubalewska-Dydejczyk A., Kulig J., Szubiński P., Mikołajczak R., Pach D., Sowa-Staszczak A., Fross-Baron K., Huszno B.: Radio-guideds Surgery (RGS) with the use of [(99m)Tc-EDDA/HYNIC]octreotate in intra- operative detection of neuroendocrine tumours of gastrointestinal tract. Eur. J Nucl. Med. Mol. Imaging , 34, 1545 (2007). 22. Iller E., Staniszewska J.: Radioisotope Centre POLATOM manufacturer of radioactive substances for medicine, science and industry. Analityka, 2, 38 (2007). 23. Iller E., Zelek Z., Konior M., Sawlewicz K., Staniszewska J., Mikołajczak R., Karczmarczyk U.: Technological line for production of carrier-free 188Re in the form of sterile isotonic solution of sodium perrhenate (VII). Proc. Ser. Trends in Radiopharmaceuticals, (ISTR-2005) IAEA, Vienna, 1, 323 (2007). 24. Iller E., Stupińska H., Starostka P.: Proporties of cellulose derivatives produced from radiation modified cellulose pulps. Rad.Phys.Chem., 76, 1189 (2007). 25. Jabłońska A., Suwalski J., Stoch P., Pszczoła J., Guzdek P., Szymański P., Pańta A.: Mössbauer effect studies of Dy(Fe0.4-xNixCo0.6)2 compounds. Nukleonika, 52 suppl., 55 (2007). 26. Józefowicz K., Golnik N., Tulik P., Zielczyński M.: Radionuclide neutron sources in calibration laboratory- neutron and gamma doses and their changes in time. Radiat. Prot. Dosim., 126, 134 (2007). 27. Klisińska M.: Present status of lead cooled fast reactors development in the context of IV generation reactors preparations. Raport IAE-128/A, Institute of Atomic Energy, (2007), in Polish. 28. Kosowicz J., Mikołajczak R., Czepczynski R., Ziemnicka K., Sowiński J.: Two peptide receptor legands 99m 3 99m Tc-EDDA/HYNIC-Tyr -octreotide and Tc-EDDA/HYNIC-DGlu-Octagastrin for scintigraphy of modullary thyroid carcinoma. Cancer Biotherapy and Radiopharmaceuticals, 22, 5, 613 (2007). 29. Latuszyński A., Pyszniak K., Droździel A., Sielanko J., Mączka D., Meldizon J.: Efficiency of the thermo - emission ion source in on-line system. Preprint IJNR P-13-9 (2007), in Russian. 30. Latuszyński A., Pyszniak K., Droździel A., Turek M., Mączka D., Meldizon J.: Atom ionization process sin the thermoionization ion source. Vacuum, 81, 1150 (2007). 31. Licki J., Chmielewski A.G., Bigos A., Jedynak A.: Monitoring system and analytical methods for electron beam flue gas treatment technology. Raport IAE-131/A, Institute of Atomic Energy, Świerk, Poland (2007). 32. Licki J., Chmielewski A. G., Bigos A.: Control systems for electron beam flue gas treatment technology. Raport IAE-130/A, Institute of Atomic Energy (2007). 33. Łuszcz M., Starzyk-Łuszcz K.: Nuclear medicine. Physics at School, 4, 15 (2007), in Polish. 34. Łuszcz M.: Nuclear power reactors. Physics at School, 1, 10 (2007), in Polish. 35. Materials investigation for power industry. Seminar. Raport IAE-127/A, Institute of Atomic Energy, Świerk, Poland (2007), in Polish. 36. Maurin J. K., Krukowski A., Czarnocki Z.: N-(2-Aminophenyl)-1- [(1s,2R)-2-hydroxy-7, 7- dimethylbicyclo[2.2.1]hept-1-yl] methannesulfonamide, a new ligand for asymmetric transfer hydrogenation. Acta Crystallogr., E63, 1593 (2007). 37. Maurin J. K., Pluciński F., Mazurek A. P., Fijałek Z.: The usefulness of simple X-ray powder diffraction analysis for counterfeit control – the Viagra example. J. Pharm. Biomed. Anal., 43, 1514 (2007). 38. Onak M., Guzdek P., Pszczoła J., Jabłońska A., Stoch P., Suwalski J., Pańta A.: Crystal structure and Mössbauer effect studies of Gd(Mn1-xFex)2 and Gd(Fe1-xCox)2 internetallics. Nukleonika, 52 suppl., 59 (2007). 39. Onak M., Guzdek P., Stoch P., Chmist J., Bednarski M., Pańta A., Pszczoła J.: Crystal structure and electrical resistivity studies Gd(Fe1-xCox)2, intermetallics. J. Alloys Comp., 433, 53 (2007). 40. Ośko J., Golnik N., Pliszczyński T.: Spectrometric measurements of 131I and 99m Tc activity in thyroid. Nucl. Instrum. Methods Phys. Res. Sect. A, 580, 578 (2007). 41. Ośko J., Golnik N., Pliszczyński T.: Uncertainties in determination of 131I activity in thyroid gland. Radiat. Prot. Dosim., 125, 1-4, 516 (2007). 42. Pawłowski M., Wojtasiewicz K., Maurin J. K., Leniewski A., Błachut D., Czarnocki Z.: The Thrope-Ingold effect in cyclic imides. Part III. Heterocycles, 71, 1743 (2007).
43. Pawłowski A., Czeppe T., Morgiel J., Górski L.: Phase composition of the plasma sprayed Al3O3 – ZrO2 layers on metallic substrate. Arch. Metall. Mater., 52, 609 (2007).
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44. Piekoszewski J., Dąbrowski L., Saratowska L., Waliś L., Barlak M., Werner Z., Kopcewicz J., Kalinowska J., Nowicki L., Ratajczyk R., Stanisławski J., Barcz A.: Austenite formation of carbon and allied steel by intense argon and nitrogen plasma pulsem: Role of carbon, chromium and nitrogen. Vaccum, 81, 1403 (2007). 45. Polański A., Słowiński B., Wojciechowski A.: Evolution of intra nuclear collisions at intermediate energies. Particl. Nuclei Lett., 4, 3 (139), 417 (2007). 46. Potempski S., Barnaba F., Galmarini S.: Numerical weather simulation in support to the CCU CAML lidar measurements: preliminary results for the case study of 21st September 2006. EUR Rep. 22855 (2007). 47. Potempski S., Galmarini S.: Ensemble for curie: contribution of ensemble v.2 to curie level 3 exercise. EUR Rep. 22755, (2007). 48. Pyszniak K., Droździel A., Turek M., Latuszyński A., Mączka D., Sielanko J., Vaganov Y. A., Yuszkievicz Y. V.: Extractions of ions from a plasma source and formation of beams. Instruments and experimental techniques, 50, 552 (2007). 49. Pyszniak K., Droździel K., Turek M., Latuszyński A., Mączka D., Sielanko J., Vaganov Y. A., Juszkevicz Y. V.: Ion extraction and ion beam formation. Pribory i Technika Eksperimenta, 4, 131 (2007), in Russian. 50. Pyszniak K., Turek M., Droździel A., Sielanko L., Mączka D.: Experimental setup for ion sputtering with medium energy ion beam. Elektronika, 10, 51 (2007), in Polish. 51. Rostocki A., Wiśniewski R., Wilczyńska T.: High pressure chase transition in rapeseed oil. J. Mol. Liquids, 135, 120 (2007). 52. Stoch L., Stoch P.: Crystal structure formation in glass from view of HRTEM. J. Therm. Anal. Calorim., 88, 2, 577 (2007). 53. Stoch P., Dziubak C., Stoch A.: Mössbauer spectroscopy of zircon ceramic pigments hematite colored. Raport IAE-132/A, Institute of Atomic energy, Poland (2007), in Polish. 54. Stoch P., Stoch A.: Nuclear waste ceramization. Mat. Ceram. 3, 95 (2007) in Polish. 55. Szawkało J., Czarnocki S. J., Zawadzka A., Wojtasiewicz K., Leniewski A., Maurin J. K., Czarnocki Z., Drabowicz J.: Enantioselective synthesis of some tetrahydroisoquinqline and tetrahydro-b-carboline alkaloids. Tetrahedron: Asymmetry, 18, 406 (2007). 56. Szteke W., Hajewska E., Baran W.: A nuclear power plants is a must. EU Magazine, 7, 42 (2007). 57. Tulik P., Golnik N., Zielczyński M.: Investigations of recombination chambers for BNCT beam dosimetry. Radiat. Prot. Dosim., 126, 274 (2007). 58. Turek M., Pyszniak K., Droździel A., Sielanko J., Latuszyński A., Mączka D., Malinowski G.: Vaganov Y.A., Juszkiewicz Y. V.: Computer modeling of ion extraction from plasma ion source. Preprint IJNR P 13-113 (2007), in Russian. 59. Tymińska K.: Monte Carlo calculations of selected dose components in head model for BNCT. Polish J. Med. Phys. Biomed. Eng., 13, 3, 127 (2007). 60. Wierzchowski W., Wieteska K., Balcer T., Malinowska A., Graeff W., Hofman W.,: Observation of individual dislocations in 6H and 4H SiC by means of back-reflection methods of X-ray diffraction topography. Cryst. Res. Technol. 42, 1359 (2007). 61. Wiśniewski R., Czachor A., Wilczyńska T., Semina W.: The influence of krypton and bismuth-krypton implantation on manganin sensitivity to temperature and hydrostatic pressure. High. Press. Res., 27, 193 (2007). 62. Wiśniewski R., Słowiński B., Didyk A. J., Wilczyńska T.: The impact of high dose implantation in to manganin on it thermal resistance properties under pressure. Vacuum, 81, 1199 (2007). 63. Wiśniewski Z., Górski L., Nowiński J., Wiśniewski R.: Crystalline precipitates in silver ion conducting materials. Solid State Phen., 130, 107 (2007). 64. Zalecki R., Stoch P., Guzdek P., Kołodziejczyk A., Pszczoła J.: Photoemission electronic state and magnetic properties of Dy(Co1-xFex)2. J. Alloys Comp., 442, 292 (2007).
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65. Zielczyński M., Golnik N., Gryziński M. A.: A comparison of different recombination methods in mixed fields at high energy accelerators. Radiat. Prot. Dosim., 126, 1-4, 248 (2007). 66. Zielczyński M., Gryziński M. A., Golnik N.: Method for determination of gamma and neutron dose components in mixed radiation Fields using a high-pressure recombination chamber. Radiat Prot. Dosim., 126, 306 (2007). 67. Zielczyński M., Rusinowski Z., Tulik P.: A sensitive neutron counter with high-pressure ionization chamber filled with BF3. Polish J. Med. Phys. Biomed,. Eng. 13, 157 (2007).
IAE REPORTS B
1. Andrzejewski K., Kulikowska T., Marcinkowska Z.: Auxiliary programs for the REBUS code. Report IAE B-7/2007, in Polish. 2. Andrzejewski K., Kulikowska T., Marcinkowska Z.: Boundary conditions for control rods of MARIA reactor. Report IAE B-6/2007, in Polish. 3. Andrzejewski K., Kulikowska T., Marcinkowska Z.: Improvement of the REBUS computational model of MARIA reactor based on the burn-up analysis. Report IAE B-5/2007, in Polish. 4. Andrzejewski K.: Monte Carlo model of Maria reactor core, graphite reflector and core caisson for BNCT therapy. Report IAE B-61/2007, in Polish. 5. Bąk R.: Nuclear Safety and Radiological Protection Program. Report 4/OR/2007, in Polish. 6. Bąk R.: Pest Control Program. Report 5/OR/2007, in Polish. 7. Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A.: Investigation of nuclear transmutation with activation detectors on “Energy plus Transmutation” setup at different beams and different energies. Report IAE B-40/2007, in Polish. 8. Boimski B., Filipiak B., Haratym Z., Józefowicz E., Kisieliński M., Major Z., Pliszczyński T., Snopek B., Sosnowiec R., Wojdowska K.: Estimation of radiological protection at Institute of Atomic Energy on the territory of Nuclear Centre Świerk and its vicinity and National Radioactive Waste Repository RóŜan (2006). Report IAE B-4/2007, in Polish. 9. Borek-Kruszewska E., Wilczek I., Zawadka A.: Procedure of grade approval tests of water meters for cold potable water and hot water. Report IAE C-15/2007, in Polish. 10. Borek-Kruszewska E.: Quality assurance program of grade approval tests of water meters for cold potable and hot water, POMPEA_TR. Report IAE B-20/2007, in Polish. 11. Borysiewicz M., Czerski Ł., Dyczewski J., Garanty I., Kowalska M., Kozubal A., Potempski S., Wasiuk A., Wojciechowicz H.: Medical procedure in case radiological hazards in urban agglomeration. Report IAE B-23/2007, in Polish. 12. Borysiewicz M., Borysiewicz M. A., Dyczewski J.: Use of HPAC package for risk simulation in release of dangerous substances in the atmosphere. Report IAE B-48/2007, in Polish. 13. Borysiewicz M., Czerski Ł., Dyczewski J., Garanty I., Kozubal A., Potempski S., Wasiuk A., Wojciechowicz H.: Model for simulation of chemical hazards in case of crisis situation in urban agglomeration. Report IAE B-22/2007, in Polish. 14. Borysiewicz M., Czerski Ł., Dyczewski J., Garanty I., Kozubal A., Potempski S., Wasiuk A., Wojciechowicz H.: The calculation models for assessment of terrorist threats in aqueous environment and urban drinking water distribution net. Report IAE B-52/2007, in Polish. 15. Borysiewicz M., Czerski Ł., Dyczewski J., Potempski S., Wasiuk A., Wojciechowicz H.: Calculation models for terrorist risk assessment in urban agglomeration. Report IAE B-51/2007, in Polish. 16. Borysiewicz M., Czerski Ł., Wojciechowicz H.: Presentation of FLUENT package capabilities. Report IAE B-53/2007, in Polish.
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17. Borysiewicz M., Garanty I., Kozubal A.: Direct costs of nuclear treaties, agreements and agencies in the nuclear nonproliferation field. Report IAE B-49/2007. 18. Broda R., Dziel T., Jęczmieniowski A., Muklanowicz A., Listkowska A.: Maintenance of the national standard unit of the radioactivity of radionuclides. Report 3/OR/2007, in Polish. 19. Broda R., Dziel T., Muklanowicz A., Listkowska A., Pieńkowski Ł., Patocka A., Kołakowska E.: International, interlaboratory and internal comparisons of measurements of radionuclide activity. Report 2/OR/2007, in Polish. 20. Bykowski W., Piąstka J., Wierzchnicka M., Rzepniewski K., Kurdej J.: Design of the flap valves in MARIA reactor fuel channels cooling system. Report IAE B-1/2007, in Polish. 21. Byszewska-Szpocińska E., Michalik J., Kaczmarczyk U., Jakubowska E.: New diagnostic kit Ig G-HYNIC labeled with technetium-99m for inflammation imaging in soft tissues and osteoarticular systems. Report/10/0R/2007. 22. Chmielewski A. G., Ostapczuk A., Licki J., Bigos A., Jedynak A.: Methods for measurements of VOC concentration in flue gas. Report IAE B-56/2007. 23. Chwaszczewski S., Szczurek J., Czerski P., Łuszcz M., Klisińska M.: Development of the road maps for nuclear option in Poland within foresight study on energy. Report IAE B-54/2007 in Polish. 24. Cieszkowska I., śółowska M., Janiak T., Piasecki A., Mielcarski M.: Optimum conditions of 57Co binding in rhodium for manufacturing of active 57Co Mössbauer sources. Report 14/OR/2007, in Polish. 25. Czachor A., Pęczkowski P.: Nuclear potential depths within the rectangular radial potential model as evaluated from experimental data on neutron scattering lengths. Report IAE B-59/2007. 26. Czerski P.: Power security in relation to nuclear power engineering. Report IAE B-19/2007, in Polish. 27. Didyk A. Yu., Komarov F. F., Vlasukova L. A., Gracheva E. A., Hofman A., Yuvchenko V. N., Wiśniewski R., Wilczyńska-Kitowska T.: Damage distributions in GaAs single crystal irradiated with 84Kr(394 MeV), 209Bi(710 Me V) and 238U(1300 Me V) swift ions. Report IAE B-24/2007. 28. Dziel T., Broda R.: Development of radionuclide standardization methods with liquid scintillators supported by Monte Carlo calculations. Report 15/OR/2007, in Polish. 29. Dziel T., Listkowska A., Broda R.: 113Sn and 99mTc activity standardization methods. Report 28/OR/2007, in Polish. 30. Filipiak B., Garboliński A., Haratym Z., Major Z., Snopek B., Wojdowska K.: Radiological protection estimate at National Radioactive Waste Repository RóŜan (2006). Report IAE B-2/2007, in Polish. 31. Frydrysiak A.: Technical project of the SAREMA system of collection and visualization dates from technological measurements in the MARIA reactor. Report IAE B-9/2007, in Polish 32. Gołąb A., Hryczuk A., Idzikowski J., Jezierski K., Jaroszewicz J., Gadoś M., Bąk A., Ośko K., Sztamborski D., Iwański I., Czarnecki M., Owsianko I., Worch Z., Polak J., Przybysz Z.: Exploitation results, examinations and measurements in the Maria reactor in the fourth quarter of 2007. Report IAE B-72/2007, in Polish. 33. Gołąb A., Idzikowski J., Jezierski K., Lechniak J., Owsianko I., Frydrysiak A., Stanaszek R., Czarnecki M., Jarzembowski P., Michalski Zb., Odziemczyk H., Iwański R., Mucha D., Bąk Z., Broda B., Skorupa S., Laskus R., Worch Z.: Exploitation results, examinations and measurements in the MARIA reactor in the first quarter of 2007. Report IAE B-3/2007, in Polish. 34. Gołąb A., Idzikowski J., Kurdej E., Bąk S., Witkowski P., Sierański K., Krawczyński D., Suchocki J., Wójcik M., Macios J., Sikorski W., Marczak R., Jędrych Wł., Grotthuss K., Nowak E.: Exploitation results, examinations and measurements in the MARIA reactor in the third quater of 2007. Report IAE B-11/2007, in Polish. 35. Golnik N.: Method for determination of total dose rate and kerma of gamma component for the purposes of neutron converter design at the reactor MARIA. Report IAE B-29/2007, in Polish. 36. Górski L., Jedynak A., Pawłowski A.: Diffraction and microscopic studies of thermally sprayed coatings. Report IAE B-21/2007.
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37. Hryczuk A., Idzikowski J., Skwarczyński M., Bąk W., Bąk M., Lech F., Lechnia T., Zawadka T., Kwiatkowski D., Hora I., Kultys W., Ćwiek W., Czerniewski W., Grzenda K., Hajkowski T.: Exploitation results, examinations and measurements in the MARIA reactor in the second quarter of 2007. Report IAE B-8/2007, in Polish. 38. Jankowska-Kisielińska J., Fijał-Kirejczyk I., Mikke K.: Anisotropy of the neutron scattering in the paramagnetic phase and on the spin-waves in the Mn0.7Ni0.3. Report IAE B-34/2007.
39. Jankowska-Kisielińska J., Fijał-Kirejczyk I., Mikke K.: Short range order in the Mn0.4Cu0.6 alloy. Report IAE B-50/2007, in Polish. 40. Jaroń A., Lipka R., Pijarowska J., Staniszewska J.: Supplement to registration documents for MBrIDA and DTPA. Report 48/OR/2007, in Polish. 41. Jaroń A., Pijarowska J., Iller E.: Preparation technology of albumin microspheres as potential radionuclide carriers for diagnosis and radiotherapy. Report 8/OR/2007, in Polish. 42. Jaroń A., Pijarowska J., Staniszewska J.: Supplement to registration documents for colloid, pyrophosphate and DMSA. Report 13/OR/2007, in Polish. 43. Jaroń A., Pijarowska J., Staniszewska J.: Supplement to HMPAO registration documents. Report 47/OR/2007, in Polish. 44. Jaroń A., Pijarowska J., Staniszewska J.: Supplement to MDP registration documents. Report 49/OR/2007, in Polish. 45. Jasiński A., Szczepaniak J.: Na131I capsules production control program. Report 30/OR/2007, in Polish. 46. Jasiński A., Szczepanik J., Szyszko T., Michalczyk P., Prokocki P., Dąbiec K., Szymański H., Zaranek J., Jęczmieniowski A., Cacko D., Janiak T.: Multigroup manipulator project: requirements, investment and construction. Report 44/OR/2007, in Polish. 47. Jasiński A.: Library management software. Report 31/OR/2007, in Polish. 48. Jasiński A.: Software for production equipment and control systems management. Report 29/OR/2007, in Polish. 49. Józefowicz K., Boimski B., Tulik P., Zielczyński M.: Radiation fields of gamma irradiator in calibration room of Radiation Protection Measurements Laboratory. IAE. Report IAE B-14/2007, in Polish. 50. Kaczarowski R.: Statistical analysis of disintegrtaion rate measurements results obtained with the 4π (LS) – γ coincidence system. Report 65/OR/2007, in Polish. 51. Kaczarowski R.: Evaluation of the uncertainty of disintegration rate measurement results obtained with the 4π(LS)-γ coincidence system. Report 32/OR/2007, in Polish. 52. Kaczarowski R.: Least squares fitting: basic notions and definitions. Report 38/OR/2007, in Polish. 53. Kilim S., Mądry M., Przyłuska J.: Introduction into problems of thorium application in nuclear power. Report IAE B-46/2007, in Polish. 54. Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A, Woźnicki Z.: Specification of the stand at the horizontal channel of the Maria research reactors for studies of transmutation of minor actinides and fission products. Report IAE B-41/2007. 55. Kilim S., Strugalska-Gola E., Woźnicki Z., Szuta M., Jędrzejec H.: Preliminary results of physical computations for the YALINA critical assembly, obtained by means of the two-dimensional neutron diffusion equation HEXAGA-II program. Report IAE B-42/2007. 56. Klisińska M.: Review of research and design studies of supercritical water-cooled reactor as IV-generation nuclear system. Report IAE B-47/2007, in Polish. 57. Klisińska M.: The SOURWAL computer code for cylindrical gamma sources, doses calculations. Report IAE B-25/2007, in Polish. 58. Kołodziejak K., Wierzchowski W., Wieteska K., Malinowski W., Graff W., Łukasiewicz T.: The investigation of structural perfection and faceting in highly Er-doped Yb3Al5O12 crystals. Report IAE B-62/2007. 59. Kozieł A., Pytel B.: Thermal and fast neutron flux density measurements within the radiation channels of MARIA reactor. Report IAE B-68/2007, in Polish.
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60. Lipka R., Jaroń A., Sasinowska I., Staniszewska J.: Supplement to Active Substance Master File for copper (I) tetra(2-methoxyisobutylisontrile) tetrafluaroroborate. Report 71/OR/2007, in Polish. 61. Lipka R., Zakrzewska E., Korytkowski M.: Method for analysis of metyl -L-α—tyrosine in radiofarmaceutical -α-metyl-tyrosine [IMT-1231]. Report 66/OR/2007, in Polish. 62. Lipka R., Staniszewska J.: Supplement to registration documents for IodoMet 123-I: purification method, quality control and ASMF for active pharmaceutical substance α-methyl-tyrosine. Report 12/OR/2007, in Polish. 63. Mądry M., Przyłuska J.: Thorium: its properties and possible use. Report IAE B-71/2007, in Polish. 64. Malinowska A., Lefeld-Sosnowska M., Wieteska K., Wierzchowski W., Pajączkowska A., Graeff W.: Conventional and synchrotron X-ray topography of defects in the core region of SrLaGaO4. Report IAE B- 70/2007. 65. Markiewicz A., Dąbiec K., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of Na131I solution. Report 21/OR/2007, in Polish. 66. Markiewicz A., Dąbiec K., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of Na131I capsules for therapy. Report 22/OR/2007, in Polish. 67. Markiewicz A., Dąbiec K., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of Na131I capsules for diagnosis. Report 23/OR/2007, in Polish. 68. Markiewicz A., Dąbiec K., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of 99mTc. Report 24/OR/2007, in Polish. 69. Markiewicz A., Dąbiec K., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of 99mTc- colloid. Report 25/OR/2007, in Polish. 70. Markiewicz A., Dąbiec K., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of 99mTc- DTPA. Report 26/OR/2007, in Polish. 71. Markiewicz A., Dąbiec K., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of 99mTc- MBrIDA. Report 27/OR/2007, in Polish. 72. Markiewicz A., Dębiec K., Korytkowski M., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of MIBG-131I for diagnosis. Report 16/OR/2007, in Polish. 73. Markiewicz A., Dębiec K., Korytkowski M., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of MIBG-131I. Report 17/OR/2007, in Polish. 74. Markiewicz A., Dębiec K., Korytkowski M., Pieńkowski Ł., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of MIBG-131I for therapy. Report 18/OR/2007, in Polish. 75. Markiewicz A., Korytkowski M., Sasinowska I., śuchlińska M.: Registration documents (CTD) for quality control of 99mTc- MDP. Report 20/OR/2007, In Polish. 76. Markiewicz A., Pieńkowski Korytkowski M., Sasinowska I.: Registration documents (CTD) for quality control of 99mTc-MIBI. Report 19/OR/2007, in Polish. 77. Markiewicz A., Szyszko T., Dąbiec K., Michalczyk P.: Validation procedure for Na131I production line (part of the registration documents). Report 40/OR/2007, in Polish. 78. Michalczyk P., Prokocki P.: The thermometers calibration documents. Report 41/OR/2007, in Polish. 79. Michalczyk P.: Service manual of computer program for controlling the mechanical and automatic cross rails, dosing and shipping system of NaI131capsule, closing machine and container labeling system of NaI131 capsules production line. Report 33/OR/2007, in Polish. 80. Mikołajczak R., Pawlak D., Garnuszek P., Marin M., Karczmarczyk U., Koumarianou E., Jęderka A.: In vitro investigations in the selected cell lines (MCF-7, COLO-205, VERO, H460, AR 42J, CTLL-2) of the affinity and internalization of radiolabeled peptides. Investigation of radiolabeled peptides binding to the cancer cell membrane preparation. Report 46/OR/2007, in Polish. 81. Mikołajczak R., Pawlak D., Pieńkowski Ł., Sawicka A.: Final development and implementation of DOTATATE-90Y and DOTATATE-177Lu based on the 2 –years experience. Report 68/OR/2007, in Polish. 82. Milczarek J. J., Fijał-Kirejczyk I., Chojnowski M., śołądek J.: Neutron radiography studies of water self- diffusion in porous medium. Report IAE B-35/2007.
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83. Milczarek J. J., Fijał-Kirejczyk I., śołądek J., Banaszak J., Jurkowski Z., śołądek J.: Neutron radiography observations of drying of kaolin samples. Report IAE B-58/2007, in Polish. 84. Milczarek J. J., Fijał-Kirejczyk I., śołądek J., Chojnowski M., Kowalczyk G.: Effect of gravitation on water migration in granular media. Report IAE B-36/2007. 85. Milczarek J. J., Fijał-Kirejczyk I., śołądek J., Iller E., Jurkowski Z., śołądek J.: Neutron diffraction (wide-and small-angle) studies of nano composite samples of WO3-ZrO2. Report IAE B-38/2007, in Polish. 86. Milczarek J. J., Fijał-Kirejczyk I., śołądek J.: Neutron radiography in research on water migration in porous media. Report IAE B-37/2007, in Polish. 87. Oonk E., Lipka R., Korytkowski M.: Supplement to registration documents of IodoMet-123I. Report 67/OR/2007, in Polish. 88. Oonk E., Byszewska-Szpocińska E., Jakubowska E.: 99mTc-HmPAO preparation kit. Report 7/OR/2007, in Polish. 89. Ośko J.: Measurements of radioiodine activity in the thyroids of iodine therapy patients. Report IAE B- 33/2007, in Polish. 90. Ośko J.: Monte Carlo simulation of NaI(Tl) detector response for 131I source in human thyroid. Report IAE B-32/2007, in Polish. 91. Paluchowska B.: Electron density characterization of thiophencarboxylic dimmers intermolecular interactions. Report IAE B-26/2007. 92. Paluchowska B.: Energy decomposition analysis of intermolecular interactions of furan carboxylic dimmers. Report IAE B-27/2007. 93. Paluchowska B.: Intermolecular interactions of heteroring oxygen and sulphure by fingerprints of Hirshfeld surface. Report IAE B-28/2007. 94. Parus J., Pawlak D., Małetka K., Mikołajczak R. Sasinowska I., Stefańczyk S.: Lutetium chloride as a labeling precursor. Part I. Report 69/OR/2007, in Polish. 95. Parus J. L.: Outline of technology for obtaining 99Mo from neutron irradiated targets less than 20% 235U enriched. Report 11/OR/2007, in Polish. 96. Parus J., Listkowska A., Mikołajczak R.: Measurement procedure for the determination of 90Sr in the eluates of 90Y. Report 51/OR/2007, in Polish. 97. Parus J., śuchlińska M.: The study of influence operating parameters of ion exchange column on the yield and purity Lutetium fractions obtained during separation of 177Lu from 169Yb. Report 9/OR/2007, in Polish. 98. Pawlak D., Mikołajczak R., Sasinowska I., Stefańczyk S., Borkowska H.: Optimization of the low activity 177Lu labeled Ca-EDTMP production kit. Report 70/OR/2007, in Polish. 99. Piasecki A., Janiak T., Barcikowski T.: Development of joining methods of materials used as windows and holders in manufacturing procedures of sealed radioactive sources: laser welding of titanium foils with solid titanium or stainless steel capsules-flux less soldering of titanium or beryllium foils with solid titanium or stainless steel capsules. Report 1/OR/2007, in Polish. 100. Piwowarczyk K., Zawadzka A., Roszkowski P., Szawkało J., Leniewski A., Maurin J. K., Kranz D., Czarnocki Z.: Enantiomers of (2R*, 3R*)-1-methyl-5-oxo-2-phenyltetrahydro-1H-pyrrolidine-3-carboxylic acid as novel chiral resolving agents. Report IAE B-18/2007. 101. Pochrybniak C., Milczarek J.J., Wieczorkowski M., Pytel K., Bojarczuk J. Radzio P.: Coolant flow driven device for uniform irradiation of solar-grade silicon wafers in reactor MARIA vertical channel. Report IAE B-60/2007. 102. Prokocki P.: Presostat calibration documents. Report 42/OR/2007, in Polish. 103. Prokopowicz R., Pytel K.: Review of the activation detectors and deconvolution algorithms for the spectrum of the thermonuclear neutrons from pulsed sources. Report IAE B-13/2007, in Polish 104. Pytel K., Kozieł A., Pytel B.: Calibration of HPGe detector for measurements of activity of minerals. Report IAE B-57/2007, in Polish. 105. Pytel K.: Evaluation of shields of the BNCT facility at the MARIA reactor. Report IAE B-73/2007, in Polish.
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106. Rusinowski Z.: The electrometer power supply. Report IAE B-39/2007, in Polish. 107. Sawicka A., Byszewska-Szpocińska E., Jakubowska E., Mikołajczak R.: Genetically engineered radionuclide-labeled monoclonal antibodies. Report 50/OR/2007, in Polish. 108. Siwicka A., Molęda Z., Wojtasiewicz K., Zawadzka A., Maurin J. K., Panasiewicz M., Pacuszka T., Czarnocki Z.: The oxidation products of melatonin derivatives show the acetylcholinesterase and butyrylcholinesterase inhibiting activity. Report IAE B-16/2007. 109. Socha D., Szymanek P., Mikołajczak W., Bąk R.: Registration documents and medical information on Na 131I capsules. Report 52/OR/2007, in Polish. 110. Socha D., Szymanek P., Mikołajczak W., Bąk R.: Registration documents and medical information on the 99mTc-Pyrophosphate preparation kit. Report 55/OR/2007, in Polish. 111. Socha D., Szymanek P., Mikołajczak W., Bąk R.: Registration documents and medical information on MIBG-131I for therapy. Report 59/OR/2007, in Polish. 112. Socha D., Szymanek P., Mikołajczak W., Bąk R.: Registration documents and medical information on the Tc-MDP preparation kit. Report 61/OR/2007, in Polish. 113. Socha D., Szymanek P., Mikołajczak W., Bąk R.: Registration documents and medical description of the 99mTc-DTPA preparation kit. Report 63/OR/2007, in Polish. 114. Socha D., Szymanek P., Mikołajczak W., Romańczuk M.: Registration documents and medical description of the 99mTc-DMSA preparation kit. Report 53/OR/2007, in Polish. 115. Socha D., Szymanek P., Mikołajczak W., Romańczuk M.: Registration documents and medical description of MIBG-123I. Report 54/POR/2007, in Polish. 116. Socha D., Szymanek P., Mikołajczak W., Romańczuk M.: Registration documents and medical description of MIBG-131I for therapy. Report 57/OR/2007, in Polish. 117. Socha D., Szymanek P., Mikołajczak W., Romańczuk M.: Registration documents and medical description of the 99m Tc-MIBI preparation kit. Report 60/OR/2007, in Polish. 118. Socha D., Szymanek P., Mikołajczak W., Romańczuk M.: Registration documents and medical description of the 99mTc-MBrIDA preparation kit. Report 62/OR/2007, in Polish. 119. Socha D., Szymanek P., Mikołajczak W., Romańczuk M.: Registration documents and medical description of the 99mTc-HmPAO preparation kit. Report 64/OR/2007, in Polish. 120. Szawkało J., Czarnocki S.J., Zawadzka A., Wojtasiewicz K., Leniewski A., Maurin J. K., Czarnocki Z., Drabowicz J.: Enantioselective synthesis of some tetrahydroisoquinoline and tetra hydro-β-carboline alkaloids. Report IAE B-17/2007. 121. Szczepanik J., Zaranek J.: Technical specification of opening, pricking and closing devices for Na131I capsules. Report 45/OR/2007, in Polish. 122. Szczurek J., Czerski P., Łuszcz M.: Mic Mac analyses concerning nuclear option within Polish energy foresight project. Report IAE B-55/2007. 123. Szteke W., Wieczorkowski M., Hajewska E., Wasiak J., Przyborska M., Rozenblicki Z., Ostrowska A.: The investigation of construction materials and its laser welded joint of the safety rods for reactor MARIA. Report IAE C-30/2007, in Polish.
124. Szuta M.: Algorithms of UO2 grain subdivision for very deep burn-up and relatively low temperature and its impact on fission gas release. Report IAE B-45/2007. 125. Szyszko T., Korytkowski M., Prokocki P.: The production room validation documents (part of the registration documents). Report 36/OR/2007, in Polish. 126. Szyszko T., Michalczyk P.: The MIBG process validation documents. Report 34/OR/2007, in Polish. 90 127. Szyszko T., Prokocki P.: Master Plan of validation of the Sr (NO3)2 productions. Report 37/OR/2007, in Polish. 128. Szyszko T., Prokocki P.: The multigroup manipulators validation documents. Report 39/OR/2007, in Polish. 129. Szyszko T., Szczepanik J., Michalczyk P.: The qualification documents of labeling system. Report 43/OR/2007, in Polish.
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90 130. Szyszko v. ChorąŜy T.: Validation documents for Sr(NO3)2 production. Report 35/OR/2007, in Polish. 131. Tymińska K.: Monte Carlo calculations of selected dose components in head model for BNCT. Report IAE B-31/2007, in Polish. 132. Tymiński Z., Leszczyńska S.: Analysis of the RC POLATOM 2007 research program relative to annual incidence rates of cancer in Poland. Report 6/OR/2007, in Polish. 133. Wieteska K., Wierzchowski W., Wierzbicka E, Malinowska A., Lefeld-Sosnowska M., Łukaszewicz T., Graeff W.: X-ray topographic study of defect structure in YVO4 crystals. Report IAE B-69/2007. 134. Wilczyńska-Kitowska T., Wiśniewski R., Czachor A., Semina V. K.: Modification of manganin properties - its sensitivity to temperature and to hydrostatic pressure - using implantation of krypton and bismuth-krypton ions. Report IAE B-67/2007. 135. Wiśniewski R., Wieteska K., Wilczyńska-Kitowska T.: Investigation of the influence of krypton and bismuth implantation on manganin sensitivity to temperature and hydrostatic pressure. Report IAE B- 63/2007. 136. Wiśniewski R., Wilczyńska-Kitowska T.: Pressure effects in phase transformations in the castor and rape oil. Report IAE B-65/2007, in Polish. 137. Wiśniewski R.: High pressure as the method of investigation of condensed phase. Report IAE B-66/2007, in Polish. 138. Wiśniewski R.: High pressure rotational rheometer with extrinsic measurement of intrinsic moment of viscosity forces. Report IAE B-64/2007, in Polish. 139. Wiśniewski Z., Milczarek J. J., Zasada D., Górski L., Jedyński M.: Structure and properties of silver ion conductors based on MoO3. Report IAE B-12/2007. 140. Wojciechowski A., Szuta M., Jędrzejec H.: Advances in the sub-critical calculations made for the Yalina thermal facility using Monte Carlo methodology. Report IAE B-43/2007. 141. Woźnicki Z.: On utility of HEXAGA codes in nuclear reactor installation computations. Report IAE B-44/2007. 142. Zielczyński M., Golnik N., Gryziński M.A.: Dosimetry in high-energy radiation fields using recombination chambers. Report IAE B-10/2007, in Polish.
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CONTRIBUTIONS TO CONFERENCES
1. Amirchonov I.V., Didyk A.Y., Muzafarov D.Z., Puzynin T.V., Puzynina T.P., Sarkar N.R., Sarharov I., Hofman A., Szarikov Z.A., Chebulukov Y.N.: Temperature effects in highly oriental pyrolitic graphite under irradiation by 86Kr and 209Bi high energy heavy ions in frame of thermal spike model. Proc. 17th Int. Conf. Radiation Physics of Solids, Sevastopol, July 9-14, 2007. 2. Andrzejewski K., Kulikowska T., Marcinkowska Z. E., Mieleszczenko W., Pytel K.: Calculations of MARIA reactor with Rebus and MCNP codes. The RERTR-2007. Int. Met. on Reduced Enrichment for Research and Test Reactors, Prague, September 23-27, 2007. 3. Artiko V., Obradović V., Petrović N., Dokić D., Janković D., Nikolić N., Popović B ., Damjanović S., Mikołajczak R., Pawlak D.: Therapy of neuroendocrine carcinomas with 90Y dota tate - preliminary results. Int. Conf. on Radiopharmaceutical Therapy (ICRT-2007) Ulaanbataar, Mongolia, September 3-7, 2007. (World J. Nucl. Med., 6, Suppl.1, 082, 58, 2007). 4. Baran W., Biłous W., Hajewska E., Szteke W., Wasiak J.: Fracture toughness and fatigue crack growth rate of steel used for Flat bottom symmetrical rails. 7th Conf. Framework Programme: Transport, Warszawa, March 1-2, 2007, in Polish. 5. Basfar A.A., Fageeha O.I., Kunnummal N., Al-Ghamdi S., Chmielewski A.G., Licki J., Pawelec B., Tymiński B., Zimek Z., Warych J.: Electron beam flue gas treatment (EBFGT) as multi-component air pollution technology. 4th Int. conf. on Air Quality, Mercury, Trace Elements SO2 Particulate Matter and Greenhouse Gases, Arlington, September 24-27, 2007. 6. Basfar A.A., Fageeha O.I., Kunnummal N., Al-Ghamdi S., Pawelec B., Chmielewki A. G., Tymiński B., Zimek Z., Licki J.: Economic feasibility of EBFGT technology for removal of pollutants from combustion of liquid fuels. IAEA Techn. Meet. on Prospects and Challenges in Application of Radiation for Treating Exhaust Gases, Warszawa, May 14-18, 2007. 7. Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A. et al.: Measurements of high energy spallation neutrons on U/Pb -assembly „Energy plus Transmutation” using Yttrium 89 as activation detectors. Int. Conf. NUCLEUS-2007. Fundamental Problems of Nuclear Physics, Atomic Power Engineering and Nuclear Technologies, Voronezh , June 25-29, 2007. 8. Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A., et al.: On results of measurements of high energy spallation neutrons on U/Pb -assembly “Energy plus Transmutation“ using Y- 89 as Activation Detectors. 4th Workshop on Neutron Measurements, Evaluations and Applications, Prague, October 16-18, 2007. 9. Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A.: Yttrium-89 detector for high energy neutron spectrum measurement of the spallation source. 9th Session of the AER Working Group- Spent Fuel Transmutation, Prague, April 10-13, 2007. 10. Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A., et al.: Measurements of high energy spallation neutrons on U/Pb -assembly „Energy plus Transmutation. Int. Conf. NUCLEUS-2007. Fundamentals Problems of Nuclear Physics, Atomic Power Engineering and Nuclear Technologies, Voronezh, June 25-29, 2007. 11. Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A.: Measurements of high energy neutrons on U/PB „Energy plus Transmutation”. School of Physics, Technology and Applications of Accelerator Driven Systems, Trieste, November 19-30, 2007. 12. Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A., Woźnicki Z.: Advance in the feasibility study to develop a stand at the horizontal channel of the MARIA research reactor for ADS related activities and to use the Hexaga code and Monte Carlo methodology to perform ADS studies. Tech. Meet. on Low Enriched Uranium (LEU) Fuel Utilization in Accelerator Driven Sub-critical Systems, Rome, November 12-16, 2007. 13. Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A.: Comparison of high energy neutron spectrum measurement of the spallation source in the last experiment with deuteron beam of energy 1.6 Ge V with the earlier deuteron beam of energy 2.52 Ge V. Tech. Meet. on Low Enriched Uranium (LEU) Fuel Utilization in Accelerator Driven Sub-critical Systems, Rome, November 12-16, 2007.
117 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
14. Bilski M., Grudziński I.P., Zdanowski R., Pietrzykowski J., Mikołajczak R., Karczmarczyk U., Garnuszek P., Dziuk E., Dąbrowski M. P., Janiak M. K.: Inhibition of nitrogen oxide (NOS) synthase influence on expression of β3 subunit of αvβ3 integrine in Lewis lung tumours inoculated in mice. 2nd Training Conf. The Isotope Diagnostic and Therapy in Oncology, Szklarska Poręba, May 31 - June 2, 2007. (Contemporary Oncology 11,4 suppl.1, P25, 17, 2007. 15. Bilski M., Grudziński I.P., Zdanowski R., Pietrzykowski J., Mikołajczak R., Karczmarczyk U., Garnuszek P., Dziuk E., Dąbrowski M.P., Janiak M.K.: Biodistribution of radioconjugate of anti β3 subunit of αvβ3 integrine monoclonal antibody in experimental Lewis lung tumours . 2nd Training Conf. The Isotope Diagnostic and Therapy in Oncology, Szklarska Poręba, May 31 - June 2, 2007. (Contemporary Oncology 11,4 suppl.1, P26, 17, 2007). 16. Bilski M., Grudziński I. P., Zdanowski R., Pietrzykowski J., Mikołajczak R., Karczmarczyk U., Garnuszek P., Dziuk E., Dąbrowski M. P., Janiak M. K.: Evaluation of affinity of radioconjugate of anti β3 subunit of αvβ3 integrine monoclonal antibody in murine endothelial and cancer cells. 2nd Training Conf. The Isotope Diagnostic and Therapy in Oncology, Szklarska Poręba, May 31 - June 2, 2007. (Contemporary Oncology 11,4 suppl.1, P27, 18, 2007). 17. Bilski M., Grudziński I. P., Karczmarczyk U., Zdanowski R., Aurin M., Mikołajczak R., Pietrzykowski J., Dziuk E. M., Dąbrowski P., Janiak M. K.: Radioimmunoscintigraphy of the β3 subunit of ανβ3 integrin as the pancarcinoma imaging modality in the experimental tumor mouse model. Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 2007, (Eur. J. Nucl. Med. Mol. Imaging, 34, suppl.2, P 466, 2007). 18. Borysiewicz M., Granaty I., Kozubal A.: Comprehensive assessment of hazard and risk generated by different fuel cycles of electric energy production-results of completed and ongoing EU programmes. 14th Sem. Materials Investigation for Power Industry, Zakopane, July 20-22, 2007, in Polish. 19. Borysiewicz M.: Cooperation with JRC institute: current state and perspectives. Co-operation of the Joint Research Centre-JRC with Polish research institution, Wrocław, July 6, 2007. 20. Borysiewicz M.: Methods of identification of accidental hazards for waterbodies –prevention, response and remediation (EU RIVER Shield Project). Training Sem. Prevention and minimalization of consequences of Major Industrial Accidents, Ustrzyki Dolne, September 25-27, 2007, in Polish. 21. Borysiewicz M.: Transport of dangerous substances. 6th Scientific Conf. Technical Safety in Chemical Industry, Plock, May 22-23, 2007, in Polish. 22. Broda R.: Some remarks on photons statistics in the LS-counter. 16th International Conference on Radionuclide Metrology and its Applications, ICRM, Cape Town, September 3-7, 2007. 23. Byszewska-Szpocińska E., Karczmarczyk U., Michalik J.: New diagnostic kit IgG -HYNIC labeled with technetium-99m for inflammation imaging in soft tissues and osteoarticular system. Responses of current Nuclear Medicine to the oncological issues, Kazimierz, September 14-15, 2007. 24. Chmielewski A. G., Licki J., Mazurek J., Belski L., Sobolewski L.: Control systems for electron Bean flue gas treatment technology. IAEA Regional Workshop on Feasibility Study for Electron Beam Flue Gas Treatment- Target Selection, Sofia, October 15-19, 2007. 25. Chmielewski A. G., Licki J., Mazurek J., Nelski L., Sobolewski L.: Control and monitoring systems for electron beam flue treatment technology. IAEA Techn . Meet. on Prospects and Challenges in Application of Radiation for Treating Exhaust Gases, Warszawa, May 14-18, 2007. 26. Chmielewski A. G., Licki J., Mazurek J., Nelski L., Sobolewski L.: Monitoring systems and analytical methods for electron beam flue gas treatment technology. IAEA Regional Workshop on Feasibility Study for Electron Beam Flue Gas Treatment- Target Selection, Sofia, October 15-19, 2007. 27. Chmielewski A. G., Licki J.: Application of electron beam for purification of exhaust gases from industrial combustion process. Environment Protection and Engineering-Sustainable Development, Krakow, July 21- 23, 2007, in Polish. 28. Chmielewski A. G., Ostapczuk A., Licki J.: Methods for VOC concentration in flue gas determination. IAEA Regional Workshop on Feasibility Study for Electron Beam Flue Gas Treatment- Target Selection, Sofia, October 15-19, 2007.
118 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
29. Chmielewski A. G., Tymiński B., Pawelec A., Zimek Z., Licki J.: Overview of the EBFGT installation solutions applicable for the gases from various fuels combustion. IAEA Techn. Meet. on Prospects and Challenges in Application of Radiation for Treating Exhaust Gases, Warszawa, May 14-18, 2007. 30. Chwaszczewski S.: High temperature reactors and its implementation in the industry. 14th Sem. Materials Investigation for Power Industry, Zakopane, July 20-22, 2007, in Polish. 31. Chwaszczewski S.: Nuclear safety. Conf. Nuclear Energy Renascence-REJ 2007, Kielce, February 12, 2007, in Polish. 32. Chwaszczewski S.: Thorium cycle in nuclear energy. Conf. Nuclear Energy Renascence -REJ 2007, Kielce, February 12, 2007, in Polish. 33. Cieszykowska I.: Radioisotope Centre POLATOM- Main Activities. 2nd Research Co-ordination Meeting (RCM) of the CRP on Small-Scale Indigenous Production of Mo-99 Using LEU Targets for Neutron Activation, Bucharest, April 16-20, 2007. 34. Ćwikła J.B., Seklecka N., Nasierowska-Guttmejer A., Jeziorski K., Mikołajczak R., Pawlak D., Walecki J.: Effects of 90Y-DOTA-TATE treatment in patients with advanced neuroendocrine tumours . 2nd Training Conf. The Isotope Diagnostic and Therapy in Oncology, Szklarska Poręba, May 31 - June 2, 2007. (Contemporary Oncology 11,4 suppl.1, P19, 13, 2007). 35. Czachor A.: Energy spectrum of the system of N using spins interacting identically-anatomy of phase transition. 5th Polish Conf. Neutron Scattering and Complementary Methods for Condensed Matter Research, Chlewiska, June 3-6, 2007. 36. Czepczyński R., Kosowicz J., Mikołajczak R., Gryczyńska M., Ziemnicka K., Sowiński J.: Scintigraphy using 99mTc-EDDA/HYNIC-TOC in diagnosis of post-surgical hypercalcitoninemia in patients with medullary thyroid carcinoma. Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 2007, (Eur. J. Nucl. Med. Mol. Imaging, 34, suppl.2, P 577, 2007). 37. Dąbrowski L., Neov S., Winek T.: Stabilization of Fe-C martensite phase by low-temperature ageing. American Institute of Physics Conf. Proc., 592, 2007. 38. Dąbrowski R., Potempski S.: Experience with RODOS in Poland during last years. RODOS Users Group, Lisbon, March, 2007. 39. Górska-Chrząstek M., Bienkiewicz M., Grzelak P., Tybor K., Zakrzewska E., Mikołajczak R., Kusmierek J. Diagnostic value of 131I-alpha-methyl-tyrosine for detection of cerebral gliomas. Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 2007, (Eur. J. Nucl. Med. Mol. Imaging , 34, suppl.2, EP 14, 2007). 40. Didyk A.Y., Hofman A., Vlasukova L.A., Gracheva E.A., Yuvchenko Y.N.: Deep damaged layer in GaAs [100] single crystal irradiated with swift 86Kr ions. Vacuum Science and Technique. Proc. 14th Scientific Conf. Minsk, October, 2007. 41. Didyk A.Y., Hofman A., Vlasukova L.A., Gracheva E.A., Yuvchenko Y.N.: Influence of inelastic energy loss of 209 Bi with energy 710 MeV and 238U with energy 1300 MeV ions on balk effects in GAaS [100] after selective chemical etching (experiments and theory). Vacuum Science and Technique, Proc. 14th Scientific Conf. Minsk, October, 2007. 42. Dziel T., Muklanowicz A.: Activity standardization of 18F and ionization chamber calibration for nuclear medicine. Radionuclides and Their Carriers for Medical and Industrial Applications, Institute of Nuclear Chemistry and Technology, Warsaw, November 21, 2007. 43. Fijałek Z., Maurin J. K.: Unusual applications of X-ray diffraction in drug control-searching for counterfeit and substandard pharmaceutical. 12th Int. Meet. on Recent Developments in Pharmaceutical Analysis (RDPA 2007), Elba, September 23-26, 2007. 44. Filipiak B., Haratym Z., Pliszczyński T.: Organization of radiological control in Nuclear Centre Świerk. 10th Meet. of Radiological Inspectors, Czerniejewo, 2007. 45. Golnik N., Zielczyński M.: Dosimetry of high-energy neutron radiation fields using recombination chambers. 2007 IEEE Nuclear Science Symp. and Medical Imaging Conf., Honolulu, October 27 – November 3, 2007. 46. Golnik N.: Dosimetry and risk management in nuclear center. Workshop on Influence of Nuclear Power Plant on Environment and Population- Methods of Measurements and Evaluation. Krakow, November 26, 2007, in Polish.
119 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
47. Golubkov D.S., Didyk A.Y., Ivanov L.I., Novakova A.A., Semina W., Hofman A.: Damage dose calculation in amorphous Fe77Ni2Si14B7 alloy irradiated on impulse neutron reactor IBR-2. Proc. 17th Int. Conf. Radiation Physics of Solids, Sevastopol, July 9-14, 2007. 48. Górska-Chrząstek M., Bienkiewicz M., Grzelak P., Tybor K., Zakrzewska E., Mikołajczak R., Kuśmierek J.: Diagnostic value of 131I-alpha-methyl-tyrosine for detection of cerebral gliomas. Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 2007, (Eur. J. Nucl. Med. Mol. Imaging , 34, suppl.2, EP 14, 2007). 49. Górski L., Pawłowski A.: Diffraction and microscopic studies of thermally sprayed coatings Size-Stain V. Diffraction Analysis of the Microstructure of Materials, Garmisch-Partenkirchen, October 7-10, 2007.
50. Górski L., Pawłowski A.: Structure and phase morphology in the coating from composites based on Al2O3 and ZrO2. 49th Polish Crystallographic Meet., Wroclaw, June 20-30, 2007, in Polish. 51. Hajewska E., Szteke W.: Baran W.: Material problems occurring in the high temperature reactors (HTR). 14th Sem. Materials Investigation for Power Industry, Zakopane, July 20-22, 2007, in Polish. 52. Hofman A., Didyk A.Y., Kochański T.: Simulation of fussion fragments influence on inner surfach of WWER and PWR cladding using swift heavy ion irradiation. Proc. 17th Int. Conf. Radiation Physics of Solids, Sevastopol, July 9-14, 2007. 53. Hofman A., Didyk A.J., Iwanow L.I., Szteke W., Hajewska E., Wagner T., Malczyk A., Wieczorkowski M.: The influence of the neutron irradiation on the chemical composition of the construction materials. 14th Sem. Materials Investigation for Power Industry, Zakopane, July 20-22, 2007, in Polish. 54. Hubalewska-Dydejczyk A., Fröss-Baron K., Mikołajczak R., Huszno B., Szybiński P., Kulig J., Januszewska A., Sowa-Staszczak A., Pach D.: The modern pre- and intraoperative diagnostic algorithm of pancreatic NET with the use of 99mTc-EDDA/HYNIC-octreate scintigraphy – the impact of SRS on patients’ management. 9th European Congress of Endocrinology, Budapest, April 28 – May 2, 2007. 55. Hubalewska-Dydejczyk A., Kulig J., Szybiński P., Mikołajczak R., Sowa- Staszczak A., Fröss -Baron K., Huszno B.: The role of radio-guided surgery (RGS) with the use of 99mTc-EDDA/HYNIC-octreotate in detection of unknown primary and secondary sites of neuroendocrine tumours of the gastrointestinal tract (GEP-NET) and improving the final outcome of patients. 9th European Congress of Endocrinology, Budapest, April 28 – May 2, 2007. 56. Hubalewska-Dydejczyk A., Stompór T., Kalembkiewicz M., Mikołajczak R., Sowa-Staszczak A., Krzanowski M., Tracz W., Pasowicz M., Kaczmarczyk U., Pach D., Huszno B., Sulowicz W.: The association between carotid artery plaque scintigraphy using 123I-labelled IL-2 and serum levels of inflammatory markers in end-stage renal disease (ESRD) patients treated with peritoneal dialysis (PD). Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 2007, (Eur. J. Nucl. Med. Mol. Imaging, 34, suppl. 2, 2007). 57. Iller E., Deptuła A., Brykała M., Sypuła M., Konior M.: Primary results of synthesis and investigations of new materials for packing of chromatographic columns of W-188/Re-188 generators. Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 13-17, 2007 (Eur. J. Nucl. Med. Mol. Imaging, 34, suppl. 2 p. 210). 58. Iller E., Deptuła A., Polkowska-Motrenko H.: Synthesis and testing of gel metal-oxide composites as filling materials for W-188/Re-188 generator columns. Radionuclides and Their Carriers for Medical and Industrial Applications, Institute of Nuclear Chemistry and Technology, Warsaw, November 21, 2007.
59. Jankowska-Kisielińska J., Fijał-Kirejczyk I., Mikke K.: Magnetic short range order In the Mn0.4Cuo.6 alloy. 5th Polish Conf. Neutron Scattering and Complementary Methods for Condensed Matter Research, Chlewiska, June 3-6, 2007.
60. Jankowska-Kisielińska J., Mikke K., Fijał-Kirejczyk I.: Diffuse neutron scattering in the Mno.4Cu0.6 alloy. 4the Eur. Conf. on Neutron Scattering, Lund, June 26-27, 2007. 61. Józefowicz E. T., Pliszczyński T., Major Z., Filipiak B., Haratym Z., Wojdowska K.: Association pour la promotion du controle de qualities des analyses de biologie medicale en radiotoxicologie . Radiotoxicology Radioactivity Meet., Avignon, June 13-15, 2007. 62. Karczmarczyk U., Maurin M., Garnuszek P., Mikołajczak R.: Investigation of Tc-99m labeling of rhIL-2 via hydrazinonicotinamide (HYNIC). Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 2007, (Eur. J. Nucl. Med. Mol. Imaging, 34, suppl.2, p 349, 2007).
120 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
63. Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A., Woźnicki Z.: Specification of the stand at the horizontal channel of the MARIA research reactor for the studies of transmutation of minor actinides and fission products. Tech. Meet. on Low Enriched Uranium (LEU) Fuel Utilization in Accelerator Driven Sub- critical Systems, Rome, November 12-16, 2007. 64. Kilim S., Strugalska-Gola E., Szuta M., Woźnicki Z.: Advance in the sub-critical calculations made for the Yalina thermal facility using two dimensional Hexaga –II code. Tech. Meet. on Low Enriched Uranium Fuel Utilization in Accelerator Driven Sub-critical Systems, Rome, November 12-16, 2007. 65. Kołodziejak K., Wierzchowski W., Łukasiewicz T., Malinowski M., Wieteska K., Graeff W.: The investigation of structural perfection and faceting in highly Er-droped Yb3Al5O12 crystals. 5th Int. Conf. on Solid State Crystals and 8th Polish Conf. on Crystal Growth, Zakopane, May 20-24, 2007. 66. Komorowski J., Szteke W., Zajączkowski P.: Repair and modernization of the clampers of high-pressure pipelines. 14th Sem. Materials Investigation for Power Industry, Zakopane, July 20-22, 2007, in Polish. 67. Korsak A., Michalik J., Mikołajczak R.: Bacteriostatis and fungistatis test as validation of sterility test method for radiopharmaceuticals. 17th Int. Symp. on Radiopharmaceutical Sciences (ISRS-07), Aachen , April 30 - May 4, 2007, (J. Labeled Compd. Radiopharm., 50 suppl. 1, 504, 417, 2007). 68. Koumarianou E., Mikołajczak R., Pawlak D., Garnuszek P., Karczmarczyk U., Maurin M., Bouziotis P., Archimandritis S. C.: Radiochemical and in vitro Evaluation of Bombesin Derivatives Labeled With Y- 90, Lu-177 And Re-188, for Targeted Radiotherapy. Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 2007, (Eur. J. Nucl. Med. Mol. Imaging, 34, suppl.2, 420, 210, 2007). 69. Koumarianou E., Mikołajczak R., Pawlak D., śuchlińska M., Pieńkowski, Ł., Zikos C., Mitsokapas N., Gourni E., Bouziotis P., Archimandritis S. C.: Labeling of bombesin analogs with Y-90, Lu-177, Re-186 and Re-188 for diagnosis and targeted therapy. 13th Pan-Hellenic Pharmaceutical Conf., May 12-14, 2007, (Eur. J. Drug Metabol. Pharmacokinet., 32, 034, 20, 2007). 70. Koumarianou E., Mikołajczak R., Pawlak D., śuchlińska M., Pieńkowski Ł., Zikos C., Mitsokapas N., Gourni E., Bouziotis P., Archimandritis S.C.: Labeling of bombesin analogs with β-emitters for targeted therapy. 17th Int. Symp. on Radiopharmaceutical Sciences (ISRS-07), Aachen, April 30 - May 4, 2007, (J. Labeled Compd. Radiopharm., 50 suppl. 1, 241, 154, 2007). 71. Koumarianou E., Pawlak D., Mikołajczak R., Garnuszek P., Karczmarczyk U., Maurin M.: Colorimetric method for quantitative determination of small peptides in pharmaceutical kits. 17th Int. Symp. on Radiopharmaceutical Sciences (ISRS-07), Aachen, April 30-May 4, 2007, (J. Labeled Compd. Radiopharm., 50 suppl. 1, 509, 422, 2007). 72. Krivopustov M.I., Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A., et al.: Investigation generations of neutrons and transmutation of I-129, Np.-237, Pu-238, Pu-241 and Am-124 using the in U/Pb -assembly “Energy plus Transmutation” setup on the JINR Synchrophrasotron /Nuclotron Proton and Deuteron Beams from 0.7 to 2.5 GeV. 15th Int. Sem. on Interaction of Neutrons with Nuclei, Dubna, May 16-19, 2007. 73. Krivopustov M. I., Bielewicz M., Kilim S., Strugalska-Gola E., Szuta M., Wojciechowski A. et al.: Investigation of transmutation of I-129, Np.-237, Pu-238 and Am 241 in fields Neutrons generated the U/Pb assembly “Energy plus Transmutation” setup at Proton and Deuteron Beams Synchrophasotron /Nuclotron by energy range from 0.7 to 2.5 GeV. Int. Conf. NUCLEUS 2007. Fundamentals Problems of nuclear Physics, Atomic Power Engineering and Nuclear Technologies, VoroneŜ, June 25-29, 2007. 74. Kubicki M., Michnowski S., Mysłek-Laurikainen B.: Seasonal and daily variations of atmospheric electricity parameters registered at the Geophysical Observatory at Świder (Poland) during 1965-2000. 13th Int.Conf. on Atmospheric Electricity, Beijing, August 13-17, 2007. 75. Kunikowska J., Hubalewska-Dydejczyk A., Sowa-Staszczak A., Królicki L., Ochman P., Mikolajczak R., Pawlak D., Kobylecka M., Mączewska J., Huszno B.: Results 90Y-DOTATATE therapy in patients with neuroendocrine tumours (NETs) - own experience. 9th European Congress of Endocrinology, Budapest, April 28 – May 2, 2007. 76. Kunikowska J., Królicki L., Mikołajczak R., Pawlak D., Hubalewska-Dydejczyk A., Sowa-Staszczak A., Pacho R., Kazbieruk M., Kobylecka M., Mączewska J.: Results of 90Y/177Lu- DOTATATE therapy in patients with neuroendocrine tumors : 1 year observation. IRIST – Beta Days in Capri, September 20–22, 2007, (Q. J. Nuclear Med. Mol. Imaging, 51, 4, 381, 2007).
121 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
77. Kunikowska J., Królicki L., Hubalewska-Dydejczyk A., Sowa-Staszczak A., Mikołajczak R., Pawlak D., Kobylecka M., Mączewska J.: Results of 90Y/177Lu- DOTATATE therapy in patients with neuroendocrine tumors- own experience of 2 years therapy. Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 2007, (Eur. J. Nucl. Med. Mol. Imaging, 34, suppl.2, 425, 2007). 78. Kunikowska J., Królicki L., Hubalewska-Dydejczyk A., Sowa-Staszczak A., Ochman P., Mikołajczak R., Pawlak D., Kobylecka M., Mączewska J.: Comparison of 90Y and mixed 90Y/177Lu labeled DOTA-TATE in the treatment of neuroendocrine tumours (NET). 2nd Training Conf.: The Isotope Diagnostic and Therapy in Oncology, Szklarska Poręba , May 31 - June 2, 2007. (Contemporary Oncology 11,4 suppl.1, 15, 9, 2007). 79. Kunikowska J., Królicki L., Mikołajczak R., Pawlak D., Hubalewska-Dydejczyk A., Sowa-Staszczak A., Pacho R., Kazbieruk M., Kobylecka M., Maczewska J.: Results of 90Y-DOTA TATE and 90Y/177Lu- DOTATATE therapy in patients with neuroendocrine tumors-own experience. Annual Congress of the European Association of Nuclear Medicine (EANM) Copenhagen, October 2007, (Eur. J. Nucl. Med. Mol. Imaging, 34, suppl.2, 424, 2007). 80. Malinowska A., Lefeld-Sosnowska M., Wieteska K., Wierzchowski W., Graeff W., Pajączkowska A.: X-ray topography of Ca0.5Sr0.5NdAl04. 49th Polish Crystallographic Meet., Wroclaw, June 20-30, 2007, in Polish. 81. Malinowska A., Lefeld-Sosnowska M., Wieteska K., Wierzchowski W., Graeff W., Pajączkowska A.: X-ray topography of Ca0.5 Sr0.5NdAl04 single crystal. 5th Int. Conf. on Solids State Crystals and 8th Polish Conf. on Crystal Growth, Zakopane, May 20-24, 2007. 82. Malinowska A., Lefeld-Sosnowska M., Wieteska K., Wierzchowski W., Graeff W., Pajączkowska A.: X-ray topography studies of growth defects in representative ABC04. 13th Int. Summer School on Crystal Growth (ISSCG-13), Park City (USA), 2007. 83. Malinowska M., Lefeld-Sosnowska M., Wieteska K., Wierzchowski W., Graeff W., Pajączkowska A.: Conventional and synchrotron x-ray topography of defects in the core region of SrLaGa04.7th Polish Met. of Synchrotron Radiation Users (7KSUPS), Poznań, September 24-26, 2007, in Polish. 84. Maurin J. K., Sarna K., Fijałek Z.: Are herbal obsesity-treatment diet supplements harmless? X-ray and HPLC studies of popular on the Polish market Chinese herbal medicines. 12th Int. Meet. on Recent Developments in Pharmaceutical Analysis (RDPA 2007), Isla of Elba, September 23-26, 2007. 85. Mikołajczak R., Pawlak D., Parus J.L.: Is 177Lu an optimal isotope for internal radiotherapy? 2nd Training Conf.: The Isotope Diagnostic and Therapy in Oncology, Szklarska Poręba , May 31 - June 2, 2007. (Contemporary Oncology 11,4 suppl.1, 13, 7, 2007). 86. Mikołajczak R.: Radioisotopes and radioligands for therapy – New Direction, plenary lecture. Int. Conf. on Radiopharmaceutical Therapy (ICRT-2007) , Ulaanbataar, Mongolia, September 3-7, 2007. 87. Mikołajczak R.: Radiolabeled octreotides (chemical aspects), plenary lecture. IRIST – Beta Days in Capri, September 20–22, 2007, (Q. J. Nuclear Med. Mol. Imaging, 51, 4, 384, 2007). 88. Milczarek J. J., Fijał-Kirejczyk I., Chojnowski M.: Neutron radiography studies of self-diffusion in water in porous medium. 4th Eur. Conf. on Neutron Scattering , Lund, June 26-27, 2007. 89. Milczarek J. J., Fijał-Kirejczyk I., Chojnowski M.: Self-diffusion in water in porous medium. 5th Polish Conf. Neutron Scattering and Complementary Methods for Condensed Matter Research, Chlewiska, June 3-6, 2007. 90. Milczarek J. J., Fijał-Kirejczyk I., śołądek J.: Water migration in granular porous media: Neutron radiography studies. 5th Polish Conf. Neutron Scattering and Complementary Methods for Condensed Matter Research, Chlewiska, June 3-6, 2007. 91. Milczarek J. J.: Application of neutron radiography in porous materials studies. IAEA Meet. on Materials Studies Using Neutrons, Vienna, July 16-19, 2007. 92. Misiuk J., Bąk-Misiuk J., Wierzchowski W., Surma B., Wieteska K., Capan I., Graeff W., Barcz A., Jung W., Antonova I.V., Prujszczyk M.: Revealing the irradiation-induced defects in Czochralski silicon by high temperature-pressure treatment. 7th Polish Meet. of Synchrotron Radiation Users (7KSUPS), Poznan, September 24-26, 2007, in Polish. 93. Neov S., Prokonenko O., Velinov N., Kozukanov V., Neov D., Dąbrowski L.: Neutron diffraction study of o LaSr3Fe3O10 in temperature range 25-650 C. American Institute of Physics Conf. Proc., 633, 2007.
122 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
94. Pawelec A., Chmielewski A.G., Tymiński B., Zimek Z., Licki J., Sobolewski L., Kostrzewski R., Mazurek J.: Experiences from operations of Pomorzany EBFGT plant and directions of technology development. IAEA Techn. Meet. on Prospects and Challenges in Application of Radiation for Treating Exhaust Gases, Warszawa, May 14-18, 2007. 95. Pawlak D., Mikołajczak R., Sawicka A., Garnuszek P., Maurin M., Karczmarczyk U., Koumarianou E.: Development of method for assessment of peptide concentration in radiopharmaceutical kits. Poster. Responses of current Nuclear Medicine to the oncological issues, Kazimierz, September 14-15, 2007. 96. Pawlak D., Mikołajczak R., Korsak A.: Preparation of therapeutic doses of DOTATATE and DOTATOC peptides labeled with 90Y and 177Lu, – summary of 2 years experience. 2nd Training Conf.: The Isotope Diagnostic and Therapy in Oncology, Szklarska Poręba May 31 - June 2, 2007. (Contemporary Oncology 11,4 suppl.1, 14, 8, 2007). 97. Pawlak D., Mikołajczak R.: Preparation of therapeutic doses of 177Lu or 90Y DOTATATE for receptor mediated radiotherapy. 2nd Int. Conf. of the European Society for Molecular Imaging, Naples, June 14-15 2007, (Molecular Imaging, 6, 6, 360, 140, 2007). 98. Pawlak D., Mikołajczak R.: Preparation of therapeutic doses of 177Lu or 90Y DOTATATE for receptor mediated radiotherapy. IRIST – Beta Days in Capri, September 20–22, 2007, (Q. J. Nuclear Med. Mol. Imaging, 51, 4, 385, 2007). 99. Pijarowska J., Jaroń A., Lipka R., Staniszewska J.: Synthesis of active substances used in radiopharmaceutical kits. Poster. Responses of Current Nuclear Medicine to the Oncological Issues, Kazimierz, September 14-15, 2007. 100. Pochrybniak C., Pytel K., Milczarek J.J., Jaroszewicz J., Lipiński M., Piotrowski T., Kansy J.: Neutron transmutation doping of multi-crystalline solar-grade silicon. 5th Polish Conf. Neutron Scattering and Complementary Methods for Condensed Matter Research, Chlewiska, June 3-6, 2007. 101. Pochrybniak C., Pytel K., Milczarek J.J., Jaroszewicz J., Lipiński M., Piotrowski T., Kansy J.: Neutron transmutation doping of multicrystalline silicon. IXth Conf. Electron Technology ELTE, Kraków, September 4-7, 2007. 102. Polański A., Słowiński B.: Problems and prospect of safe and waistless production of nuclear energy. Conf. Energex , Singapore, November 26-30, 2007. 103. Potempski S., Galmarini S., Bianconi R.: Multiscale ENSEMBLE exercise: objectives and analysis. Ensemble Technical Workshop, Ispra, May 14-16, 2007. 104. Potempski S., Galmarini S.: ETEX-2 exercise: ENSEMBLE analysis. ENSEMBLE Technical Workshop, Ispra , May 14-16, 2007. 105. Rajewska A., Mędrzycka K., Hallman E.: SANS method study of aggregation in mixed solutions of nanonic and catonic classic surfactants. 4th Eur. Conf. on Neutron Scattering, Lund, June 26-27, 2007. 106. Rajewska A.: SANS method study of aggregation in mixed micellar solutions nanionic and cationic. 21st Conf. Eur. Colloid and Interface Society, Geneva, September 10-14, 2007. 107. Rajewska A.: SANS study of the gemini nonionic surfactant in micellar solutions. BENSC User’s Meet. Hahn-Meitner Institute, Berlin, Germany, Berlin, May 23-25, 2007. 108. Roszkowski P., Szawka J., Czarnocki S., Maurin J. K., Zawadzka A., Leniewski A., Czarnocki Z.: Stereo selective synthesis of some isoquinoline and β – carboline derivatives of pharmacological importance. 41st IUPAC World Chemistry Congress, chemistry Protecting Health, Natural environment and Cultural Heritage, Turin, August 5-11, 2007. 109. Sawicka A., Byszewska E., Mikołajczak R.: Modification of monoclonal antibody fragments scFvTU20 in order to improve labeling conditions when labeled to therapeutical radioisotopes. Initial report. Poster. Responses of Current Nuclear Medicine to the Oncological Issues, Kazimierz, September 14-15, 2007 . 110. Sawicka A., Byszewska-Szpocińska E., Mikołajczak R., Konrad L., Sedlacek J., Mudra M.: Radiolabeled Engineered Antibodies scFvTU20 as targeting agents for tumor diagnosis and therapy. Radionuclides and Their Carriers for Medical and Industrial Applications, Institute of Nuclear Chemistry and Technology, Warsaw, November, 21, 2007. 111. Słowiński B., Sobczak R., Wojciechowski A.: Investigation of the correlation between the multiplicity, rapidity and impact parameter of hadron -nucleus interactions in the Ge V energy range. 6th Conf. on Nuclear and Particle Physics, Luxor, November 17-21, 2007.
123 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
112. Słowiński B.: New parameterization of longitudinal and lateral fluctuations of electromagnetic showers in dense amorphous materials. Workshop Physics of PANDA, Dubna, July 3, 2007. 113. Słowiński B.: Observation of pionic degrees of freedom in quasifree channels of πA interactions at several Ge V/c. 1st Workshop, Dubna, May 10, 2006. Proc., Dubna, 2007. 114. Staniszewska J., Sasinowska J.: Application of ICP-OES in quality control of radiopharmaceuticals and radioactive products. Sem. of Atomic Spectrometry, Ustroń, September 17-19, 2007. 115. Stoch P., Stoch L.: Cs containing borosilicate waste Glassed. NATO Adv. Res. Workshop, 8th Sem. Porous Glasses- Special Glasses. Porous Glass Technology for Detection of Chemical Agents, Wroclaw, September 4-8, 2007. 116. Stoch P., Ciecińska M., Stoch A.: Nuclear waste ceramization. 6th Conf. Polish Ceramic Society, Zakopane, September 13-16, 2007. 117. Szczurek J., Chwaszczewski S., Czerski P., Łuszcz M.: Nuclear power component in foresight on energy in Poland. Int. conf. Nuclear Energy for New Europe, Portorož, September 10-13, 2007. 118. Szczurek J.: Safety aspect of advanced nuclear power reactors. 14th Sem. Materials Investigation for Power Industry, Zakopane, July 20-22, 2007, in Polish. 119. Szteke W., Baran W., Wagner T. Hajewska E.: Radiological monitoring of the airports. Conf. on Transport, 7th Framework, Warszawa, March 1-2, 2007, in Polish.
120. Szuta M.: Comparison of fission gas products accumulated in the irradiated UO2 fuel with the radiogenic gas trapped in minerals containing fissile atoms. 7th Int. Conf. on WWWR Fuel Performance, Modeling and Experimental Support, Albena, September 17-21, 2007.
121. Szuta M.: Mechanisms identical nature of noble gas accumulation in the irradiated UO2 fuel an din the mineral materials containing fissile atoms. Int. Workshop Towards Nuclear fuel Modeling in the Various Reactor types Across Europe, Karlsruhe, June 25-25, 2007. 122. Szybiński P., Klek S., Kulig J., Hubalewska A., Mikołajczak R., Sowa-Staszczak A., Huszno B.: [99mTc- EDDA/HYNIC] octreotate – a new 99mTc-labelled radiopharmaceutical for radioguided surgery in the diagnosis and treatment of neuroendocrine tumours of gastrointestinal tract (GEP-NET). 42th World Congress of Surgery of the Int. Society of Surgery ISS/SIC Int. Surgical Week ISW 2007, Montreal, August 26–30, 2007. 123. Tulik P., Golnik N., Zielczyński M.: Recombination methods and detectors for boron neutron capture therapy. 15th National Scientific Conf. on Biocybernetics and Biomedical Engineering, Wroclaw, September 12-15, 2007, in Polish. 124. Tulik P.: Application of recombination chambers at research irradiation facilities for BNCT at reactor MARIA in Poland. Young Researcher BNCT Meet., Birmingham, September 20-21, 2007. 125. Turek M., Pyszniak K., Droździel A., Sielanko J., Mączka D.: Simulation of beam extraction from hollow cathode ion Source. 5th Int. Conf. NEET, Zakopane, July 12-15, 2007. 126. Wagner T.: Material Research Laboratory. Hot cells in Institute of Atomic Energy in Świerk. Association Days-EURATOM- IFPiLM, Kudowa Zdrój, September 17-20, 2007, in Polish. 127. Wierzchowski W., Wieteska K., Graeff W. (invited lecture): Synchrotron topographic investigations of SiC bulk crystals and epitaxial layers. 2nd Polish-Japanese-German Crystal Growth Meet., Zakopane, May 20-24, 2007. 128. Wierzchowski W., Wieteska K., Balcer T., Malinowska A., Graeff W., Hofman W.: Observation of individual dislocations In 6H and 4H SiC by means of back-reflection methods of X-ray diffraction topography. 5the Int. Conf. on solids state Crystals and 8th Polish Conf. on Crystal Growth, Zakopane, May 20-24, 2007. 129. Wierzchowski W., Wieteska K., Balcer T., Malinowska A., Graeff W., Hofman W.: Application of back- reflection topographic methods for identification of dislocations in 6h and 4h SiC crystals. 7th Polish Meet. of Synchrotron Radiation Users (7KSUPS), Poznań, September 24-26, 2007, in Polish 130. Wieteska K., Chwaszczewski S.: Energy and economic development in Poland. 14th Sem. Materials Investigation for Power Industry, Zakopane, July 20-22, 2007, in Polish.
124 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
131. Wieteska K., Wierzchowska K., Wierzbicka E., Malinowska A., Lefeld-Sosnowska M., Łukaszewicz T., Graeff W.: X-ray topographic studies of defect structure In YV04 crystals. 7th Polish Meet. of Synchrotron Radiation Users (7KSUPS), Poznań, September 24-26, 2007, in Polish. 132. Wilczyńska T., Wiśniewski R., Czachor A., Semina V.K.: Modification of manganin properties - its sensitivity to temperature and hydrostatic pressure - using krypton and bismuth-krypton. 5th Int. Conf. New Electrical and Electric Technologies and their Industrial Implementation, Nee T 2007, Zakopane, June 12-15, 2007. 133. Wiśniewski R., Wieteska K., Wilczyńska T.: Investigation of the electric thermopower of the Kr ion implanted manganin-Cu thermocouple. 5th Conf. New Electrical and Electric Technologies and their Industrial Implementation, Nee T 2007, Zakopane, June 12-15, 2007. 134. Wiśniewski R., Wilczyńska T.: Post pressure effects in castor and rapeseed oils phase changes. 39th Congress of the Polish Physical Society, Szczecin, September 9-14, 2007, in Polish. 135. Wiśniewski R.: High pressure rotational rheometer with external system for measurement of inner viscosity force moments. Ist Congress of the Polish Mechanics, August 28-30, 2007, in Polish. 136. Wiśniewski R.: High pressures as methodology for condensed phase investigation. 5th Polish Conf. Neutron Scattering and Complementary Methods for Condensed Matter Research, Chlewiska, June 3-6, 2007, in Polish. 137. Wiśniewski Z., Górski L., Zasada D., Milczarek J. J.: Investigation of structure and conductivity of superionic conducting materials on the basis of silver iodide. 49th Polish Crystallographic Meeting, Wrocław, June 28-30, 2007. 138. Wiśniewski Z., Górski L., Zasada D.: Investigation of structure and conductivity of superionic conducting materials on the basis of silver iodide. 5th Polish Conf. Neutron Scattering and Complementary Methods for Condensed Matter Research, Chlewiska, June 3-6, 2007. 139. Wojciechowski A., Szuta M.: Advance in the sub-critical calculations made for the Yalina thermal facility using Monte Carlo methodology. Tech. Meet. on Low Enriched Uranium (LEU) Fuel Utilization in Accelerator Driven Sub-critical Systems, Rome, November 12-16, 2007. 140. Wojdowska W.: Advantages of W188/Re188 generator and it’s potential applications. 2nd Training Conf. The Isotope Diagnostic and Therapy in Oncology, Szklarska Poręba, May 31 - June 2, 2007. 141. Woźnicki Z.: The solution of continuous-time algebraic Riccati equations by means of the Sor -like method. MAT TRIAD 2007 Workshop, Będlewo, March 22-24, 2007, in Polish. 142. Yuvchenko Y., N., Didyk A. Y., Vlasukova L. A., Hofman A., Gracheva E. A.: Thermal effects in 209Bi (710 Me V) ion tracks at GaAs single crystal in frame of thermal peak. Proc. 17th Int. Conf. Radiation Physics of Solids, Sevastopol, July 9-14, 2007. 143. Zajączkowski P., Wasiak J., Biłous W., Szteke W., Przyborska M.: Diagnostic of thick wall elements of the high pressure pipelines. 14th Sem. Materials Investigation for Power Industry, Zakopane, July 20-22, 2007, in Polish. 144. Zielczyński M., Golnik N., Gryziński M. A.: Dosimetry of high-energy neutron radiation fields using recombination chambers. 14th National Meet. of Polish Society of Radiation Research, Kielce, September 24-26, 2007, in Polish.
BOOKS
Licki J., Chmielewski A.G., Ostapczuk A., Zimek Z.: VOCs removal from exhaust gases using an electron beam accelerator. In: Environmental Engineering, Eds. Pawłowski L., Dudzińska M., Pawłowski A. London, Taylor and Francis, pp. 355-358 (2007).
Neov S., Prokonenko O., Velimov N., Kozukarov V., Neov D., Dąbrowski L.: Oxygen nonstoichometry study of LaSr3Fe3O10 in the temperature range 25-650 °C. In: Nuclear methods in non-nuclear applications. Ed. by Ch. Soyanov, Sofia, Herom Press, pp. 219-255 (2007).
125 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
Filipiak B., Haratym Z., Józefowicz E.T., Pliszczyński T.: NPL Environmental radioactivity proficiency test exercise. Teddington, National Physical Laboratory (2007).
Haratym Z., Fillipak B., Józefowicz E.T., Golnik N., Józefowicz K., Pliszczyński T., Major Z., Śniegoń W., Zielczyński M., Boimski B., Ośko J.: Quality manual procedures for Radiation Protection Measurements Laboratory of Institute of Atomic Energy, Rev. ed., Warszawa, Polish Centre for Accreditation (2007).
Chwaszczewski S., Szczurek J., Czerski P., Klisińska M., Łuszcz M.: Characteristics of technology sectors, In: Technological development scenarios of the fuel-energy system for assuring the polish energy security. Part 1: Study of the fuels and energy management for development of the Polish Energy Foresight within 2005-2030. Katowice, p. 72, Central Mining Institute (2007), in Polish.
Chwaszczewski S., Szczurek J., Czerski P., Klisińska M., Łuszcz M.: Scenarios of the technological development for energy sector areas In: Technological development scenarios of the fuel-energy system for assuring the polish energy security. Part 1: Study of the fuels and energy management for development of the Polish Energy Foresight within 2005-2030. Katowice, p. 109, Central Mining Institute (2007), in Polish.
Chwaszczewski S., Szczurek J., Czerski P., Klisińska M., Łuszcz M.: Scenarios of the technological development for energy sector areas, In: Technological development scenarios of the fuel-energy system for assuring the polish energy security. Part 2: Scenarios developed using on Polish Energy Foreside within 2005-2030, Katowice, pp. 184- 194, Central Mining Institute (2007), in Polish.
Chwaszczewski S.: Spent fuel management in Poland. In: Safety related issues of spent nuclear fuel storage, pp. 37- 54, Springer (2007).
Broda R., Cassette P., Kossert K.: Radionuclide metrology using liquid scintillation counting. Metrologia, Monograph BIMP, 44, 1-17, p. 36-S52 (2007).
Pawlak D., Korsak A., Mikołajczak R., Janota B., Karczmarczyk U., Jakubowska E.: Preclinical Evaluation of therapeutic radiopharmaceuticals based on 90Y and 177Lu. In: Technical reports series no. 458, IAEA, pp. 217-232 (2007).
Nickel F.: Energy loss of swift ions in polycrystalline targets. IAE Monographs vol. 11, Institute of Atomic Energy, Świerk, Poland (2007).
PATENTS
Method for determination of the dose rate ratio in two component radiation fields. Application P 38243 High pressure rotational rheometer with extrinsic measurement of intrinsic moment of viscosity forces. Application P-382321 Pharmaceutical gammaglobulin kit and way of produce of the gammaglobulin radiodiagnostic preparation, PL 371 176, 27.09.2007 (J. Michalik, U. Karczmarczyk, A. Markiewicz) Electroless ruthenium plating of metals, PL 193725, 30.03.2007 (M. Mielcarski) Radioactive core of iodine-125 ophthalmic applicator and the method of manufacturing, PL 194367, 31.05.2007 (M. Mielcarski, T. Barcikowski)
Ph. D.THESIS
M. Sc. Izabela Cieszykowska, Ph.D. Thesis: Electrochemical processes of fixing of radionuclides applied in sealed sources for brachytherapy, Institute of Nuclear chemistry and Technology, public defense October 27, 2007
M. Sc. Wioletta Wojdowska, Ph. D. Thesis: Biodegradation of hydrocarbons vaccum fraction of crude oil, Technical University of Lodz, public defense January 16, 2007
126 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
SEMINARS ORGANIZED BY IAE
XIV SEMINAR MATERIALS INVESTIGATION FOR POWER STATIONS AND POWER INDUSTRY 20-22 June 2007 Zakopane CHAIRMAN: E. Hajewska SCIENTIFIC PROGRAM COMMITTEE E. Hajewska - LBM IEA Świerk-chairman J. Buzek –European Parliament, Energy and Research Commission O. Gajl - Ministry of Science and Higher Education J. Pilarczyk-Institute of Welding St. Soja-Ministry of Economy St. Szpilowski – PAA K. Wieteska – IAE ORGANIZING COMMITTEE W. Szteke – chairman J. Wasiak- secretary W. Biłous , M. Przyborska , T. Wagner, J. Wojciechowska B. Zubowski
This was the 14th seminar on the subject covered a range of application areas occurring Turing the exploitation of power plants as well as the exploitation of gas transport pipelines and in the underground gas storages. The attention to the security of gas installation was call. The technical supervision in the light Poland accession to the European Union are also discussed. The special session was destined to present some aspect connected with the future of nuclear energy in Poland. There were six session: - Energy in Poland and European Union - High temperature reactors - The other problem of nuclear energy - Diagnostic investigation in the power industry - Welding-novelties and exploitation problem - Operating problems of the gas pipelines- European standards and modern technologies
PROGRAMME
I. Session 1. Buzek J.: Safety atomic energy for Europe and Poland 2. Wieteska K., Chwaszczewski S.: Energy and economic development in Poland
II. Session 3. Sławiński A.: Materials research for energy technologies in FP.7 4. Chwaszczewski S.: High temperature reactors and its implementation in the industry 5. Michalik J.: Manufacture of the fuel components for high temperature reactors 6. Hajewska E., Szteke W., Baran W.: Materials problems occurring in the high temperature reactors(HTR.)
III. Session 7. Szczurek J.: Safety aspect of advanced nuclear power reactors 8. Hofman A., Didyk A. Ju ., Iwanow L. I., Szteke W., Hajewska E., Wagner T., Malczyk A., Wieczorkowski M.: The influence of neutron irradiation on the chemical composition of construction materials 9. Kolano R., Szynowski J., Polak M.: Rapidly-quenched Cu-based alloys and their application In nu clear engineering
IV. Session 10. Wojas M.: NDT employment in monitoring the state of material at High Temperature pressure equipment 11. Zagórski A., Spychalski W., Mizera J.: Continuous monitoring of propagating damages in the pipeline 12. Komorowski J., Szteke W., Zajączkowski P.: Repair and modernization of the clampers of high-pressure pipelines
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13. Zajączkowski P., Wasiak J., Biłous W., Szteke W., Przyborska M.: Diagnostics of thick wall elements of high pressure pipelines 14. Zantowicz B.: Investigations overview of selected critical parts of BC50 power generation set-13HMF and 10H2M steels 15. Borysiewicz M., Garanty I., Kozubal A.: Comprehensive assessment of hazard and risk generated by different fuel of electric energy production-results of completed and ongoing EU programmes
V. Session 16. Pilarczyk J.: Developments in welding and joining methods of metallic materials 17. Szubryt M., Brózda J., Czaja G.: Properties of bainitic T/P24 steel welded joints 18. Pasternak J.: Technological recommendations, properties and experience of welding joints on hest resisting martensitic steels designated into superheater for supercritical; parameters
VI. Session 19. Kalinowski K., Dąbrowski A., Sobkiewicz D., Oracz H.: New method of leak detecting In diagnostics of gas pipeline system 20. Olma T., Winckowski J.: Contemporary methods if emergency repair works on transit pipelines 21. Witek M.: Upgrade of pipelines operated in polish conditions in accordance with European Standards
WORKSHOP RADIONUCLIDES AND THEIR CARRIERS FOR MEDICAL AND INDUSTRIAL APPLICATIONS 21 November 2007 Warsaw
CONTRIBUTORS:
IChTJ - Institute of Nuclear Chemistry and Technology, Warsaw, Poland POLATOM - Institute of Atomic Energy, Radioisotope Centre POLATOM, Otwock-Świerk, Poland NPI -Nuclear Physics Institute, Academy of Science of the Czech Republic, Řež, Czech Republic HIL - Heavy Ion Laboratory, University of Warsaw, Warsaw, Poland ITE - European Commission, Joint Research Centre, Institute for Transuranium Elements, Karlsruhe, Germany Duke University - Duke University Medical Center, Durham, North Carolina, USA IMC - Institute of Macromolecular Chemistry, Academy of Science of the Czech Republic, Prague, Czech Republic NRI - Nuclear Research Institute, Řež, Czech Republic IMG - Institute of Molecular Genetics, Academy of Sciences of the Czech Republic, Prague, Czech Republic IMB - Institute of Molecular Biology, Slovak Academy of Science, Bratislava, Slovak Republic FZR - Institute of Radiopharmacy, Forschungszentrum Rossendorf/Dresden, Germany ITN - Instituto Tecnologico e Nuclear, Sacavem, Portugal Aristotle University - School of Pharmacy, Aristotle University of Thessaloniki, Greece
SCIENTIFIC PROGRAMME INTRODUCTION
J. Narbutt (IChTJ): Chemical studies for design and production of new radiopharmaceuticals (POL-RAD-PHARM) – a research-training project in the 6. FP of EU, the action Marie Curie Host Fellowships for Transfer of Knowledge
Part 1. Radionuclides
- E. Iller, A. Deptuła, H. Polkowska-Motrenko (POLATOM and IChTJ): Synthesis and testing of gel metal- oxide composites as filling materials for W-188/Re188 generator columns - J. Ráliš, K. Eigner Henke, O. Lebeda, J. Kučka, J. Štursa, J. Kučera and F. Melichar (NPI): Production of 86Y on cyclotron U-120M in Řež - J. Choiński, K. Kilian, D. Hechner (HIL) : The Warsaw PET Centre – possibilities for production of metallic PET radionuclides - T. Dziel (POLATOM): Activity standardization of 18F and ionization chamber calibration for nuclear medicine. - B. Zielińska, C. Apostolidis, F. Bruchertseifer, A. Morgenstern (ITE): Improved method for the production of 225Ac/213Bi for targeted alpha radiotherapy
128 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
Part 2. Radionuclide carriers
- M. Pruszyński, A. Bilewicz, M. Zalusky (IChTJ and Duke University): Complexes of 211At with Rh3+ and Ir3+ as precursors of therapeutic radiopharmaceuticals - M Hrubý, J. Kučka, O. Lebeda, K. Ulbrich (IMC and NRI): Thermoresponsive polymers for local radiotherapy - Sawicka, E. Byszewska, R. Mikołajczak, L. Kronrad, J. Sedlacek, M. Mudra (POLATOM, NRI, IMG and IMB): Engineered radionuclide-labelled antibodies, preliminary 125I iodination results - E. Gniazdowska, P. Koźmiński, U. Kuenstler, H.-J. Pietsch (IChTJ and FZR): Towards Tc(III)- or Re(III)- labelled peptides with tunable lipophilicity - L. Fuks, E. Gniazdowska, P. Koźmiński, D. Papagiannopoulou (IChTJ and Aristotle University): Tricarbonyltechnetium(I) complex with substituted propanoic acid 99m + - L. Fuks, M. Neves (IChTJ and ITN): Towards complexes with the [ Tc(CO)3] core for targeted radiotherapy - J. Palige, G. Zakrzewska-Trznadel, A. Miśkiewicz (IChTJ): Generator-based radiotracers for industrial applications
IAE SEMINAR
Snopek B.: Radiological consequences assessment of anti-rocket shield installation in Poland - information about activities of the Nuclear Safety and Radiation Protection Commission, Council for Atomic Energy, March 1, 2007, in Polish. Kilim S., Mądry M.: Thorium perspectives in nuclear energy, April 26, 2007, in Polish.
Zielczyński M.: Dosimetry of high energy radiation fields using recombination chambers, November 22, 2007, in Polish.
Filipek S. (Institute of Physical Chemistry PAS, Warszawa): On the synthesis and properties of new hydrides (deuterides) - possible applications in hydrogen storages, March 29, 2007, in Polish.
DEPARTMENT OF NUCLAER METHODS IN THE SOLID STATE PHYSICS SEMINARS
1. Droździel A. (UMCS Lublin): Creation and utilization of ion beams for ion implantation, January 11, 2007, in Polish.
2. Nowakowski R. (Institute of Physical Chemistry PAS, Warsaw): High resolution investigation of physico- chemical processes on surface of solid state using STM and ATM, January 25, 2007, in Polish.
3. Jankowska-Kisielińska J.: On mechanisms of spin-glass and short-range formation in the Cu-Mn alloys, February 8; 22, 2007, in Polish.
4. Wiśniewski R.: High pressures as method for the solid-state investigation, May 11, 2007, in Polish.
5. Milczarek J. J.: The self-diffusion of water of water in porous media: neutron radiography studies, May 24, 2007, in Polish.
6. Wiśniewski Z.: Nanotechnology and the global warming, June 14, 2007, in Polish.
7. Fritz-Popowski G. (University of Gratz): Indirect Fourier transformation and its application to small-angle X-ray scattering data, July 24, 2007.
8. Czachor A.: Theory lattice dynamics, with Mg taken as an example-resume, October 11, 2007, in Polish.
9. Guzdek A. (AGH Kraków): Electrical and magnetic properties and superfine interactions in the Y/Gd (M/L)2: M, L-Fe, Co, Ni compounds, October 25, 2007, in Polish.
129 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
10. Pęczkowski P.: Diffraction - interference phenomena supporting the wave nature of light and of material particles (neutrons, fullerens), November 8, 2007, in Polish.
11. Dobrzyński L.(IPJ Świerk): Charge, spin and electron momentum distribution - in the search of wave functions, November 29, 2007, in Polish.
RADIOISOTOPE CENTRE POLATOM SEMINARS
1. Byszewska E.: New diagnostic kit IgG -HYNIC labeled with technetium 99m for inflammation imaging in soft tissues and osteoarticular system, November 29, 2007, in Polish.
2. Iller E.: Determination of activation conditions of gels in nuclear reactor MARIA and its radiochemical and metrological evaluations, November 29, 2007, in Polish.
3. Koczarowski R.: Development of uncertainity evaluation methods for radioactivity measurements performed using the National standard of Radionuclide Activity Unit calibration equipment, December 4, 2007, in Polish.
4. Tymiński Z.: Analysis of RC POLATOM research programme 2007 based on Annual Incidence Rates of Caner in Poland, December 4, 2007, in Polish.
5. Listkowska A.: Study of measurement procedure for determination of SR 90 impurities in Y-90 eluents , December 6, 2007, in Polish.
6. Pijarowska J.: Elaboration of the preparation technology of albumin microspheres as a potential radionuclide carriers for diagnostic and therapeutic use, December 6, 2007, in Polish.
7. Mikołajczak R.: In vitro investigations In the selected cell lines (MCF-7, COLO-205, VERO, H460, AR 42J, CTLL-2) of the affinity and internalization of radiolabelled peptides. Investigation of radiolabeled peptides binding to the cancer cell membrane preparation, December 6, 2007, in Polish.
8. Sawicka A.: Engineered radionuclide-labeled monoclonal antibodies, December 13, 2007, in Polish.
9. Dziel T.: Development of radionuclides standardization methods by means of liquid scintillators technique with use of Monte Carlo calculations, December 13, 2007, in Polish.
10. Cieszykowska I.: Development of the optimum conditions of 57Co in rhodium in aspect of manufacturing of 57Co active for Mössbauer sources, December 18, 2007, in Polish.
11. Piasecki A.: Development of joining methods of materials used as windows and holders in manufacturing procedures of sealed radioactive sources: laser welding of titanium foils with solid titanium Or stainless steel capsules-fluxes soldering of titanium or beryllium foils with solid titanium or stainless steel capsules, December 20, 2007, in Polish.
12. Zakrzewska E.: Development of formulation of EDTMP kit for labeling with low specific activity lutetium, December 20, 2007, in Polish.
13. Broda R.: International inter-laboratory and internal comparisions of measurements of radionuclide activity, December 20, 2007, in Polish.
14. Broda R.: Application and keeping of the national standard unit of the radioactivity of radionuclides, December 20, 2007, in Polish.
130 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
LECTURES AND SEMINARS DELIVERED OUT OF THE IAE
Czachor A.: Neutron scattering on elementary excitations in disordered magnets using the Green’s function method-the equal-acces -splitting. Institute of Theoretical Physics, University of Wroclaw, December 12, 2007, in Polish.
Milczarek J.J.: Neutron radiography studies of porous media, Institute of Technology and Chemical Engineering, Poznań University of Technology, January 26, 2007, in Polish.
Słowiński B.: General physics. Radiation phenomena in materials. Physics background of nuclear power. Lectures in Warsaw University of Technology, in Polish.
Słowiński B.: Nuclear energy, Warsaw University of Technology, December 12, 2007, in Polish.
Bielewicz M.: Measurements of high Energy Neutrons on U/Pb assembly “Energy plus Transmutation”. Int. Centre of theoretical Physics, Trieste, November 25, 2007.
POLISH AND INTERNATIONAL RESEARCH PROJECT
Grant no 3 T10C 022 29, 2005-2007. Investigation of defect structure, lattice deformation and polytypic structure in single crystals and implanted layers of silicon carbide, W. Wierzchowski, Institute of Electronic Materials Technology in cooperation with K.Wieteska
Contract: FI6R-CT-2004-508843, 2005-2008. European approach to nuclear and radiological emergency management, EURATOM acronym: EURANOS, M. Borysiewicz
International experiment “Energy plus Transmutation” on Research of Physical aspects of electronuclear method of energy production and transmutation of radioactive wastes of nuclear energetic in high energy beam of particles from synchrophrasotron or nuclotron accelerator in JINR, Dubna , Prof. A. I. Malachov, Dr M. I. Krivopustov in cooperation with M. Szuta, E. Strugalska-Gola, S. Kilim, A. Wojciechowski M. Bielewicz; 1999-2007
Project: Coordinated Research Project on Analytical and Experimental Benchmark Analyses of Accelerator Driven System (ADS). IAEA Research Agreement No: 13396, 2005 - 2010, M. Szuta, Z. Woźnicki, E. Strugalska-Gola, S. Kilim, A. Wojciechowski, A. Polański
European Approach to Nuclear and Radiological Emergency Management EURANOS, integrated project, 2004 – 2007, M. Borysiewicz
CONRAD (COordinated Network for Radiation Dosimetry), FP6-12684 (2005-2007), Coordinated by Delft University, The Netherlands, Work Package 6 Complex mixed radiation fields at workplaces, Contract no: FP6- 12684 (2005-2007), N. Golnik
Development of recombination methods for the dosimetry of high-energy radiation fields, with regard to the new international recommendations. 2 P05D 065 30, 10.04.2006 - 09.04.2009, N. Golnik
Optimization of the neutron beam spectrum and collimation at the boron neutron capture therapy facility, using numerical modeling of the converter/moderator/filter system and neutron transport in the patient head phantom. PZB/MEiN/01/2006/43, 2007-2009, N. Golnik
EUTERP – European Training and Education in Radiation Protection Platform, N. Golnik
Project N508 048 31/2569: Neutron transmutation doping of multicystalline silicon for photovoltaic applications. J. J. Milczarek
131 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
Project 3T08D04630: Glassy materials for radioactive and toxic waste immobilization, 2006 – 2009, P. Stoch
Project 3T10C 00628: Rheological properties of the new phase of castor oil and the design of the original rheometer. 2005 – 2007, R. Siegoczyński, R. Wiśniewski, A. Rostocki, T. Wilczyńska
Project of collaboration on ion implantation with JINR Dubna, Contract number 07-5-1013-2001-2008, R. Wiśniewski
Project 3T08D 4530: Structure and properties of diphase conductors of silver, 2006 – 2007, Z. Wiśniewski
Project N 505 0875 33: Rheological properties of the new high-pressure castor oil phase. Project and realization of a original rotational rheometer, 2007 – 2009, R. Wiśniewski, T. Wilczyńska, D. Tefelski
Improvement of electrical characteristics of special alloys and products based on the alloys by heavy ion implantation. Cooperation agreement Institute of Atomic Energy Świerk, Poland with Joint Institute for Nuclear Research, Dubna, Russia, no. 3760-5-06/08, 2006 – 2009: Aleksandr J. Didyk (IJNR), R. Wiśniewski (IAE)
RADIOSOTOPE CENTRE POLATOM RESEARCH PROJECT
Development of methods for preparation and investigation of receptor specific ligands labeled with radioactive isotopes for oncological diagnostics, molecular imaging and targeted receptor therapy, 2 P05A 024 28, 2005-2008, R. Mikołajczak
New technology of isotope generators 188W/188Re preparation based on the materials for filling of chromatographic columns obtained by sol-gel method, 3 T09B 042 29, 2005-2008, E. Iller
Electrochemical processes of fixing of radionuclides applied in sealed sources for brachytherapy, 1 T09B 046 30, 2007, M. Mielcarski
Development of techniques for preparation of biodegradable microspheres as potential radionuclide carriers for isotope diagnostics and therapy, R05 025 01, 2006-2009, E. Byszewska-Szpocińska
Engineered radionuclide-labeled antibodies, EUREKA/54/2005, 2006-2009, R. Mikołajczak
New diagnostic kit IgG -HYNIC labeled with technetium -99m for inflammation imaging in soft tissues and osteoarticular system , 6 T09 2004 C/06358, 2004-2007, J. Michalik, E. Byszewska-Szpocińska
Research agreement IAEA 12880: Development of generator technologies for therapeutic radionuclides, 2004-2008, R. Mikołajczak
6th Framework Programme Priority FP6-2003-Lifescihealth-I-LSH-2003-1.2.2-2- A Network of Exellence for Identification of New Molecular Imaging Markers for Diagnostic Purposes (DIMI-Diagnostic Molecular Imaging); FP6-2003-Lifescihealth-I-LSH-2003-1.2.2-2; 512146
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SPECIAL PROGRAMMES AND RESEARCH DEVICES
The financial support for the Hot Laboratory of the Material Research Laboratory of IAE Head of project: W. Szteke Project no: 624/E-80/SPUB/ZR6/058/2007
JOINT SCIENTIFIC AND TECHNOLOGY PROJECT SCIENTIFIC AND TECHNOLOGICAL COOPERATION JOINT PROJECT
COST (European Cooperation in the field of Scientific and Technical Research) Projects D18 WG-4 Lanthanides used in therapy. Radiolanthanides emiting particles and stable lanthanides emiting radiation under the influence of exterior irradiation, 2004-2008 D38 WG-3 Metal based system for molecular imaging applications. Isotope probes for molecular imaging, 2006-2011 BM 0607 Targeted radionuclide therapy, 2007-2011
IAEA Research Agreement Development of therapeutic radiopharmaceuticals based on 177Lu for radionuclide therapy, 2006-2009
FRANCE LABORATORIE LEON BRILLOUIN CEN, Saclay Inelastic Magnetic Neutron Scattering at the Magnetic Brillouin Zone Boundary in the Mn (20%Fe) Alloy; Anisotropy of Spin Wave Dispersion in the FCC Mn (37%Fe) Alloy, B. Hennion Polish side partners: K. Mikke, J. Jankowska-Kisielińska
RUSSIA JOINT INSTITUTE FOR NUCLEAR RESEARCH, DUBNA Investigation of surfactants aggregation in micellar water solutions A. Rajewska
Determination of Dosimetric Parameters of Medical High-Energy Radiation Beams Prof. E. A. Krasavin . Polish side Partner: M. Zielczyński
Experiments on the Accelerator Complex of the LHE JINR (project ENERGY-TRANSMUTATION) Prof. A .I. Malachov, Dr M.I. Krivopustov Polish side partners: Z. Strugalski, E. Strugalska-Gola, A. Wojciechowski, M. Bielewicz
Laboratory of High Energies Study of Transmutation of Radioactive Waste of Nuclear Energy Arrangements Prof. A .I. Malakhov Polish side partner: B. Słowiński
BAUMAN STATE TECHNICAL UNIVERSITY, MOSCOW B. E. Vintaikin INSTITUTE OF METAL PHYSICS, MOSCOW Investigation of Atomic and Magnetic Microdynamics, Structural Effects Close to Martensitic Phase Transitions and Kinetics of Phase Decompositions in the 3d Metal Alloys E. Z. Vintaikin Polish side partners: K. Mikke, J. Jankowska-Kisielińska, J. J. Milczarek
133 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
ROSTOV STATE UNIVERSITY, ROSTOV-ON-DON Iterative methods prof. L. A. Krukier Polish side partner: Z. I. Woźnicki
INSTITUTE OF NUMERICAL METHODS AT RUSSIAN ACADEMY OF SCIENCES, MOSCOV Reactor Physics Numerical Methods prof. V. Lebedev, prof. Y. Neczepurenko Polish side partner: Z. I. Woźnicki
SWITZERLAND CERN Measurements of Dose Equivalent in High-Energy Radiation Fields. Radiation Protection Group of CERN Dr T. Otto Polish side partners: N. Golnik, M. Zielczyński
GERMANY Consortium FEMOTOPHYSICS for the collaboration of Poland with FAIR Program. B. Słowiński, member as a representative of IAE Gesellschaft für Schwerionenforschung , Darmstadt Proton-Antiproton-Darmstadt–PANDA Collaboration: GSI-international program of construction of new multi- purpose detector for investigation of fundamental properties of matter B. Słowiński, member
BELGIUM FREE UNIVERSITY OF BRUSSELS Reactor Physics prof . R. Beauwens Polish side partner: Z. I. Woźnicki
NUCLEAR PHYSICS INSTITUTE OF THE ACADEMY OF SCIENCES, PRAHA, Nuclear Reactions of Intermediate Energy in Extended Heavy Targets Prof. R. Mach Polish side partner: B. Słowiński
EGYPT NUCLEAR RESEARCH CENTER, CAIRO Radiation Materials Investigation Using Beams of Heavy Ions, Neutrons and Gamma Rays Prof. M. N. H. Comsan Polish side partner: B. Słowiński
EDUCATION
IAE provides access to nuclear facilities for education purposes. In 2007 over 5000 visited Institute of Atomic Energy in order to obtain information on atomic energy, nuclear techniques and their applications in industry, agriculture, health and environment protection. The visitors represented universities, engineering colleges, secondary school and various scientific and technical organizations. The main topic of interest was reactor MARIA research reactor and with its installations and facilities. Another point of interest was Material Research Laboratory and its research activity for power industry. Each visit comprised the lecture on the principles of the nuclear reactor operation and the applications of the neutron radiation. In total 132 lectures on the nuclear energy have been delivered at the MARIA reactor and 74 similar lectures on the methods of materials testing were given at the Material Research Laboratory.
134 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
EDUCATION FOR PERSONNEL FOR NUCLEAR POWER AND NUCLEAR MEDICINE. POSTGRADUATE STUDIES OF NUCLEAR METHODS AND ENGINEERING
S. Chwaszczewski –Member of Council Association as a representative of Institute of Atomic Energy B. Słowiński – Member as a representative of the Faculty of Physics, Warsaw University of Technology.
VISITORS in IAE
V. K. Lukyanov - Joint Institute for Nuclear Research, Dubna, Russia A. Yu. Didyk - Joint Institute for Nuclear Research, Dubna, Russia W. K. Semina - Joint Institute for Nuclear Research, Dubna, Russia
TRAINING OF STUDENTS
Adam Michalak, Grzegorz Paw 10 – 25.09.2007, AGH University of Science and Technology, Kraków
Eftichia Koumarianou (Greece), 01.10.2006 - 31.07.2007 (Cooperation program in culture, education and associated fields between the Republic of Poland and the Government on the Republic of Greece
Loi Cheng Hang Humphrey (China), 02.07.2007 – 12.08.2007 (research training based on the agreement of the International Association for the Exchange of Students for Technical Experience (IAEST)).
Sebastien Marcinek (France), 13.05.2007 – 15.08.2007, DUT Measures Physiques, IUT L. Pasteur, Schiltigheim, France
Katarzyna Jakubik 02.07.2007 – 31.08.2007, Department on Chemical and Process Engineering, Warsaw University of Technology.
LONG TERM VISITS OF IAE STAFF MEMBERS TO FOREIGN COUNTRIES
T. Kochański Joint Institute for Nuclear Research, Dubna , Russia December 2008
A. Rajewska Joint Institute for Nuclear Research, Dubna , Russia December 2008
A. Hofman Joint Institute for Nuclear Research, Dubna , Russia December 2008
D. Mączka Joint Institute for Nuclear Research, Dubna , Russia Contract: 2006 – 2008.
L. Dąbrowski Institute for Nuclear Research and Nuclear
Energy, Sofia, Bulgaria December 2007
S. Potempski Institute of Environment and Sustainability of
The Joint Research Centre, Ispra , Italy January – December 2007
135 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
VISITS OF RADIOISOTOPE CENTRE POLATOM STAFF TO FOREIGN COUNTRIES
Participation in EMIL European Network in Torino – Training, Imaging probes, Chemical separation techniques. Italy – Torino, 16 – 21 April, 2007. R. Lipka, A. Jaroń
DIMI/EMIL annual meeting- 2 nd Int. Conf. - European Society for Molecular Imaging. Italy – Neapol, 12– 15 April, 2007. E. Byszewska–Szpocińska, D. Pawlak
DIMI/EMIL summer school in Prague Czech Republic – Prague, 29 – 31 August, 2007. A. Sawicka
PARTICIPATION IN SCIENTIFIC COUNCILS, COMMITEES AND OTHERS
POLISH ACADEMY OF SCIENCES COMMITTEEES
Committee of Medical Physics and Radiobiology of Polish Academy of Sciences N. Golnik Polish Academy of Sciences, Energy Studies Committee S. Chwaszczewski
INTERNATIONAL ORGANISATIONS, ASSOCIATIONS AND SOCIETIES
International Organization of Medical Physics President of the Polish National Memeber Society, M, 2002. N. Golnik International Radiation Protection Association N. Golnik, B. Filipak, K. Józefowicz, M. Zielczyński International Organization for Standardization. Working Group WG-19 N. Golnik, K. Józefowicz, M. Zielczński, B. Filipiak (Working Group WG-14) International Society of Neutron Capture Therapy, International Society for Cf-252 Brachytherapy N. Golnik (Member) European Radiation Dosimetry Group (EURANOS) N. Golnik International Linear Algebra Society (ILAS) Z. I. Woźnicki Society for Industrial and Applied Mathematics (SIAM) Z. I. Woźnicki Gesellschaft für Angewandte Mathematik and Mechanic (GMM) Z. I. Woźnicki World Scientific and Engineering Society Z. I. Woźnicki Technical Committee on Nuclear and Hazardous Waste Verification (TC 5) P. Stoch Joint Institute for Nuclear Research, Dubna , Laboratory of High Energies B. Słowiński (as a refere for scientific publications) International Scientific Collaboration PANDA, GSI, Darmstadt B. Słowiński (Member)
136 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
American Association for the Advancement of Sciences M. Szuta American Chemical Society M. Szuta World Energy Committee: European Regional Study Working Group on the Future of Nuclear Energy in Europe S. Chwaszczewski (Member) Members of European Association of Nuclear Medicine (EANM) R. Mikołajczak (Member of Radiopharmacy Committee of EANM since 2001), E. Iller, D. Pawlak
Society of Radiopharmaceutical Science, SRS R. Mikołajczak
International Research Group in Immuno-Scintigraphy and Therapy, IRIST R. Mikołajczak Country Coordinator of European Radiopharmacy Courses R. Mikołajczak
Council for Atomic Energy Matters R. Mikołajczak (Member 2005 – 2008)
2nd Section (Radioactive measurement) Consultative Committee for Ionizing Radiation (CCRI) in the International Bureau of Weights and Measures (BIPM) in Sevres, France R. Broda (Member since 1995)
International Committee of Radionuclide Metrology (ICRM), LSCWG R. Broda (Member since 1978)
Nuclear Medicine Review R. Mikołajczak (Member of Editorial Board since 2001)
Journal Nuclear Engineering and Design A. Strupczewski (permanent Board Member)
Institute of Nuclear Materials Management J. Kozieł (Member)
Journal of Powder Diffraction L. Górski (Corresponding Member of the Editional Staff)
International Scientific Journal of Nuclear and Radiation Physics, Cairo, Egypt B. Słowiński
POLISH ORGANISATIONS, ASSOCIATIONS AND SOCIETIES
President of Polish Nuclear Society S. Chwaszczewski
Polish Society of Medical Physics Vice President, 2005 N. Golnik
Atomic Council of Polish Atomic Energy Agency N. Golnik (Member of Radiological Protection Commission)
Polish Society of Radiation Research N. Golnik, M. Zielczyński
137 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
Commission on Nuclear Safety and Radiological Protection N. Golnik
Polish Physical Society A. Czachor, K. Mikke
Polish Neutron Scattering Society A. Czachor, K. Mikke, J. J. Milczarek, J. Jankowska-Kisielinska
Polish Committee for Standardization J. Licki (Member of Problem’s Commission no 280 – Air Quality) M. Szuta (Member of Problem’s Commission no 266 –Nuclear Instrumentation) J. Wojnarowicz (Member Technical Committees since 1997)
Society of Electricians of Poland, Nuclear Power Section E. Strugalska-Gola
The Ministry of Education S. Słowiński (referee for high School manuals of physics)
Committee of the Nuclear Methods for Condensed Phase Physics: Council for Atomic Energy Matters A. Czachor, J. J. Milczarek, K. Wieteska
Polish Synchrotron Scattering Society K. Wieteska
Polish Solar Energy Society, Polish Photovoltaics Society Polish Society of Solar Energy PTES-ISES C. Pochrybniak
Committee on Nuclear Energy S. Chwaszczewski
Council for Atomic Energy Matters G. Krzysztoszek
Polish Journal of Medical Physics and Engineering, I, 2005 M. Zielczyński
Polish Association of Nuclear Medicine, PTMN R. Mikołajczak, E. Byszewska-Szpocińska, D. Pawlak, A. Sawicka, J. Pijarowska
Polish Pharmacopoeia Committee, Radiopharmaceutical Committee, R. Mikołajczak (Member since 2006)
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SCIENTIFIC, TECHNICAL AND ECONOMIC INFORMATION CENTRE Ewa Szlichcińska
LIBRARY [email protected] Ewa Szlichcińska M. Sc. Gabryela Kosicka The library contains 17.790 volumes and 1040 journal volumes, 60 current journals in the field covered by IAE research activity and serves as the national source of literature on nuclear techniques and radioactive waste management.
PUBLISHING ACTIVITY GraŜyna Swiboda M. Sc. Jadwiga Pustoła Publications IAE: 6 IAE Raports A, 1 IAE Monograph, IAE Annual Report 2006
POPULARIZATION ACTIVITY Gabryela Kosicka Hanna Gryzińska
The activity of the Scientific, Technical and Economic Information Centre consists of: - collecting and disseminating information in the field of occupational nuclear energy, physics of condensed matter, radiation protection and environment - preparing modern information materials, organization exhibitions, fairs and presentations - publishing activity - provides organization and support for visitors of the IAE - standardization activity
RADIOISOTOPE CENTRE POLATOM LIBRARY Małgorzata Rozum, [email protected] Tel. 022 718 07 08 The library contains 12.047 volumes and 214 journal volumes, 47 current journals (including 41 polish journals and 6 foreign) in the fields of radiology and nuclear medicine, isotopes and radiation applications, chemistry.
Promotion of IAE Participation in ENEX 10 th International Power Industry Fair and Fair of Renewable Sources of Energy, Kielce, February 12-14, 2007 Participation in International Poznan Fair: Innovations, Technologies, Machines: Science for Economy, Poznań, July 20-23, 2007
STANDARDIZATION ACTIVITY TK nr 266 for Nuclear Instrumentations
Roman Trechciński Ph.D.,D.Sc Klemens Kruszewski M. Sc. Stefan Wójtowicz Ph.D.,D.Sc
The Standardization Committee for Nuclear Instrumentations has been active since January 2003. The Technical Committees are composed of expert affiliated to national administration, agencies, business, employers, consumers, professional, science and technology high education associations and PKN employers. President of the Polish Committee for Standardization in accordance with solution of the Normalization Council of PKN, recommended to organize in the Institute of Atomic Energy at Świerk, appropriate technical committee for standardization of nuclear instrumentations and for designing the Polish Standards for nuclear instrumentations, apparatus for nuclear reactor and radiological needs.
139 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
The Technical Committee nr 266 for Nuclear Instrumentations collaborate with the following international organizations:
CENELEC/SR 45; CENELEC/SR 45A ; CENELEC/SR 45B; CENELEC/TC 45A; CENELEC/TC 45B; IEC/TC 45; IEC/TC 45/SC 45A; IEC/TC 45/SC 45B.
Standardization documents completed in 2007: pr PN-EN 61582 Radiation protection instrumentation - in vivo counters classification, general requirement and test procedure for portable and installed equipment. pr PN-EN 60761-4 Equipment for continuous monitoring radioactivity in gaseous effluents -Part 4: Specific requirements for iodide monitors. pr PN-EN 60761-1 Equipment for continuous monitoring radioactivity in gaseous effluents -Part 1 General requirements. pr PN-EN 60601-2-II Medical electrical equipment-Part 2-II; particular requirements for the safety of gamma beam therapy equipment. pr PN-EN 6035 Radiation protection instrumentation-alpha beta and alpha/beta (beta energy>60 keV ) contamination meter and monitors.
The opinion of the CENELEC standard: EN-6060-2-9; 1996. Medical Electrical Equipment Part 2 -9. Particular requirements for the safety of patient contact dosimeters used in radiotherapy with electrically connected radiation detectors. Standardization Commission for Interfaces and Buildings Electronics Systems, Area No 173
Standardization Commission for Interfaces and Buildings Electronics Systems, Area No 173 prPN-prEN 14908-5 Open data Communications In building automation, controls and building management- control network protocol-part 5: Implementation guideline prPN -prEn 15500 Control for HVAC applications-electronic individual zone control equipment prPN -prEN 50174-1 Information technology-cabling installation-part 1: Specification and quality assurance, prPN -prEn 50174-2 Information technology-cabling installation-part 2: Installation planning and practices inside buildings prPN-prEN-50491-3 General requirements for home and building electronic systems( HBES) and building automation and control systems (BACS) – part 3: Electrical safety requirements prPN -prEN 50491-5-1 General requirements for home and building electronic systems( HBES) and building automation and control systems (BACS) – part 5-1: EMS requirements, conditions and tests set-up prPN -prEN 50491-5-2 General requirements for home and building electronic systems( HBES) and building automation and control systems (BACS) - part 5-2 EMC requirements for HBES/BACS (class A) used in residential prPN -prEN 50491-5-3 General requirements for home and building electronic systems( HBES) and building automation and control systems (BACS) -part 5-3 EMC requirements for HBES/BACS (class B) used in residential, commercial and light industry environment
140 ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education
prPN -prEN 50491-5-4 General requirements for home and building electronic systems( HBES) and building automation and control systems (BACS) -part 5-4: EMC requirements for HBES/BACS used industry environment prPN -prEN ISO 16484-5 Building automation and control systems-part 5: Data communication protocol PN-EN 50090-5-3:2007 Home and building electronic systems(HBES)-part 5-3 Media and media dependent layers-radio frequency PN-EN 50173-1:2007(U) Information technology-generic cabling systems-part 1: general requirements PN-EN 50173-2:2007(U) Information technology-generic cabling systems-part 2: Office premises PN-EN 50173-3:2007(U) Information technology-generic cabling systems-part 3: Industrial premises PN-EN 50173-4:2007(U) Information technology-generic cabling systems-part 4: Homes PN-EN 50173-5:2007(U) Information technology-generic cabling systems-part 5:Data centers PN-EN 50310:2007 Applications of equipotential bonding and earthing in buildings with information technology equipment Pn -EN 50346:2004/A1 :2008/(U) Information technology-cabling installation-testing of installed cabling PN –EN ISO 16484 -3:2007 Building automation and control systems(BACS)-part 3: Functions prPN -EN 14908-1 Open data communication in building automation, controls and building management- control network protocol-part 1: Protocol stack PN-EN 13312-1:2007 Open data communication in building automation, controls and building management- home and building electronic system-Part 1: Product and system requirements PN-EN 13321-2:2007 Open data communication in building automation, controls and building management- home and building electronic system-Part 2KNXnet/IP communication PN-EN 14597:2007 Temperature control devices and temperature limiters for heat generating systems PN-EN 14908-2:2007 Open data communication in building automation, controls and building management- home and building electronic system-control network protocol-Patr2:Twisted pair communication PN-EN 14908-3:2007 Open data communication in building automation, controls and building management- home and building electronic system-control network protocol-Part 3: Power line channel specification PN-EN 14908-4:2007 Open data communication in building automation, controls and building management- home and building electronic system-control network protocol-Part 4: IP Communication PN-EN 15232:2007(U) Energy performance of buildings-impact of building automation, controls and building management PN-EN 500065-4-7:2007 Signaling on low-voltage electrical installation in the frequency range 3 kHz to 148,5 kHz and from 1,6 MHz to 30 MHz-Part 4-7: Portable low voltage decoupling filters-safety requirements PN-EN 50090-2-2002/ A2/2007 Home and building electronic systems(HBES)-Part:2-2-System overview-general technical requirements PN-EN 50090-5-1:2007 Home and building electronic systems(HBES)-Part 5-1: Media and media dependent layers-power line for HBES Class 1 prPN -EN 15232 Energy performance of buildings-impact of building automation, controls and building management prPN -EN 50173-2 Information technology-generic cabling systems-Part 2: Industrial premises prPN -EN 50174-3 Information technology-generic cabling systems-Part 3: Industrial premises prPN -EN 50173-4 Information technology-generic cabling systems-Part 4:Homes
141 Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007
prPN -IEC 62050 VHDL Register Transfer Lever (RTL) synthesis prPN -IEC 62243 Artificial intelligence exchange and service tied to all test environments(Al-ESTATE)
COMPUTER CENTRE A. Szarek, I. Wasilewski, G. Jaworski, P. Zduńczyk Computer network in the Institute of Atomic Energy is based on the star topology with individual twisted pair or fiber optic cables coming from each node and terminating at central network concentrator or hub/switch. The total lengths the fibre-optic cable is about 3600 meters. There are about 220 connected workstations, mostly PC computers. Network is split into 3 virtual LANs. Two of them cover both segments of thick ethernet cable. The third is a special area called demilitarized zone (DMZ) consisting of two servers. VLANs are connected by a second layer switch Cisco 2950-24. Communication with the internet is realized through the SDSL link with a speed of 2Mbit/s. Router Lucent Technologies DSL-HST-E that connects the institute’s network to internet node in NETIA, is separated from the switch by a firewall. Firewall is an OpenBSD server running packet filter. There are two machines working in DMZ. One of them is a PC machine on FreeBSD Unix, that acts as a name resolver (DNS), mail, http and ftp server. The second one is Hewlett Packard 9000 A-400 used for complex mathematical computation. Local network, server area and the internet are strictly separated from each other. Communication between VLANs is routed, NATed and protected by a firewall: - Communication between machines in the local network and internet can be initiated only by a local machine. - Communication between machines in the local network and DMZ can be initiated only by a local machine. - Computers can access the FreeBSD server from the internet only for specific services such as e-mail, ftp and http. - HP A-400 machine can be accessed only from the local network or from the safe FreeBSD server. Those rules guarantee easy access to the internet and local servers for local users and good protection against intrusion. In addition e-mail service is protected by the Kaspersky Anti-Virus Bussiness Optimal scanner.
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AUTHOR INDEX
Andrzejewski K. 20 Kacprzyk W. 81 Kapuściński J. 98 Balzarini J. 67 Karczmarczyk U. 98 Banaszak J. 61 Kilim S. 35, 36 Bielewicz M. 36 Klisińska M. 39 Boimski B. 31 Kołakowska E. 100 Borysiewicz M. 80, 81, 82, 83, 84, 85, 89, 90 Kołodziejak K. 56 Borysiewicz M. A. 90 Konior M. 99, 102 Broda R. 100, 101, 103 Kowalczyk G. 60 Byszewska-Szpocińska E. 95, 98 Kowalski G. 55 Kozubal A. 82, 84, 85 Chmielewski A. G. 91 Krukowski A. 66 Chojnowski M. 60 Krzysztoszek G. 15 Chwaszczewski S. 40 Kulikowska T. 20 Cieszykowska I. 96 Kuśmierek J. 98 Czachor A. 49, 50, 53 Czarnocki Z. 66 Lefeld-Sosnowska M. 54, 57 Czerski Ł. 82, 85, 90 Licki J. 91 Czerski P. 40 Listkowska A. 100
De Cargouet G. 35 Łukasiewicz T. 56, 57 Didyk A.Yu. 71, 72 Łuszcz M. 40 Droździel A. 74, 75 Duda P. 42, 43 Malinowska A. 54, 57 Dyczewski J. 82, 85, 90 Malinowski M. 56 Dziel T. 95, 100, 103 Małetka K. 95 Dzikowski W. 42 Marcinkowska Z. 20 Markiewicz A. 95 Fijał-Kirejczyk I. 59, 60, 61, 62 Maurin J. K. 66, 67 Filipiak B. 23 Mączka D. 74, 75 Michalik J. 98 Galmarini S. 87, 88 Mielcarski M. 96 Garanty I. 82, 84, 85 Mikke K. 59 Golnik N. 23, 26, 27, 28, 30 Mikołajczak R. 95, 99 Gołąb A. 15 Milczarek J. J. 49, 50, 58, 60, 61, 62 Górska-Chrząstek M. 98 Muklanowicz A. 100 Górski L. 70 Graeff W. 54, 55, 56, 57, 58 Orzeszko A. 67 Gronkowski J. 55 Orzeszko B. 67 Gryziński M.A. 26, 29 Ostapczuk A. 91 Guzdek P. 63, 64 Ośko J. 28
Haratym Z. 23 Paluchowska B. 68, 69 Parus J.L. 99 Iller E. 62, 97, 102 Patocka A. 100 Patrycy A. 45 Jankowska-Kisielińska J. 49, 59 Pawlak D. 99 Jaroń A. 97 Pawłowski A. 70 Jaroszewicz J. 15 Pęczkowski P. 53 Jaworska K. 45 Pieńkowski Ł. 100 Jędrzejec H. 82 Pijarowska J. 97 Józefowicz E. T. 23 Pliszczyński T. 23 Józefowicz K. 23, 31 Pochrybniak C. 58 Jurkowski Z. 60, 61, 62 Polkowska-Motrenko H. 102
143 Potempski S. 81, 82, 85, 86, 87, 88 Tulik P. 31 Pszczoła J. 63, 64 Turek M. 74, 75 Pyszniak K. 74, 75 Wasiuk, A. 82, 85 Saniewski G. 45 Wawszczak D. 102 Semina V. 72 Wierzbicka E. 57, Sielanko J. 74, 75 Wierzchowski W. 54, 55, 56, 57, 58 Sikorski M. 43 Wieteska K. 54, 55, 56, 57, 58 Słowiński B. 41, 42, 43, 71 Wilczyńska T. 71, 72, 73 Słupiński T. 55 Wiśniewski R. 71, 72, 73 Snopek B. 23 Wojciechowicz H. 82, 85, 90 Sobczak R. 41 Wojciechowski A. 35, 36, 38 Stoch A. 63, 64 Woźnicki Z. 35 Stoch P. 63, 64, 65 Wójcik T. 63, 64, 65 Strugalska-Gola E. 35, 36 Strupczewski A. 44, 45 Zachariasz P. 63, 64, 65 Suwalski J. 63, 64, 65 Zielczyński M. 26, 27, 30, 31 Szczurek J. 40 Zuchlińska M. 99 Szteke W. 52 Szuta M. 35, 36, 37, 38 Żołądek Jan 60, 61, 62 Żołądek Joanna 60, 61, 62
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