institute of atomic energy

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

I

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

II

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

III

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 Yb3Al 5O12 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

IV

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

V

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

VI

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

Departmentof Nuclear Methods

in Solid State Physics

Departmentof Nuclear Energy

Cyfronet Computing Center

Information Center

DEPUTY DIRECTORFOR NUCLEAR SAFETYAND RADIOLOGICAL

PROTECTION

DEPUTY DIRECTORFOR REACTORS

SCIENTIFIC SECRETARYDEPUTY DIRECTOR

Department of Maria Reactor

Departmentof Reactor Analysis

and Technology

DEPUTY DIRECTORFOR ADMINISTRATION

AND MAINTENANCE

CHIEF ACCOUNTANT

DIRECTORNUCLEARSAFETY

COMMISSION

SCIENTIFICCOUNCIL

CENTRE OF EXCELENCEMANHAZ

MATERIAL RESEARCH LABORATORY

RADIATION PROTECTIONMEASUREMENTS

LABORATORY

ORGANIZATION SCHEME

RADIOISOTOPE CENTREPOLATOM

ANNUAL REPORT 2007 General Information

5

MANAGING STAFF Director

Krzysztof Wieteska, Ph.D., D.Sc.

Phone 022 718 00 01

Scientific Secretary, Deputy Director

Stefan Chwaszczewski, Ph.D., D.Sc.

Phone 022 718 00 04

Deputy Director, Administration and Maintenance

Henryk Michałowski, M.Sc.

Phone 022 718 00 03

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 Radiation Protection Jerzy Kozieł, M.Sc.

Phone 022 718 03 33

RESEARCH DEPARTMENTS AND LABORATORIES

B2 Department of Nuclear Methods

in the Solid State Physics

Prof. A. Czachor, Ph.D., D.Sc. Phone 022 718 01 18

B3 Department of Nuclear Energy Prof. S. Chwaszczewski, Ph.D., D.Sc. Phone 022 718 00 30 022 718 03 04

LBM Material Research Laboratory W. Szteke, M.Sc. Phone 022 718 00 61

NC Centre of Excellence MANHAZ M. Borysiewicz, Ph.D.

Phone 022 718 01 32

NS Radiation Protection Measurement Laboratory

Z. Haratym, Ph.D.

Phone 022 718 02 00 022 718 00 32

SLN Regional Laboratory of Neutronography

J. J. Milczarek, Ph.D.

Phone 022 718 02 33

BC Computing Center CYFRONET A. Szarek Phone 022 718 00 18

OINTEA Scientific, Technical and Economic Information Centre

E. Szlichcińska, M.Sc. Phone 022 718 00 07

POLATOM Radioisotope Centre K. Małetka Ph.D. Phone 022 718 07 00

General Information ANNUAL REPORT 2007

6

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


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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: . Deputy secretary: Teresa Kulikowska, Ph.D.

Edmund Kmiotek, Ph.D.


8

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


9

Prof. Mieczysław E. Poniewski Ph.D., D.Sc. Kielce University of Technology, Warsaw University of 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

Prof. Tadeusz Wasiutyński Ph.D., D.Sc. Institute of Nuclear Physics, Polish Academy of Sciences, 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.


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SCIENTIFIC STAFF PROFESSORS

Stefan Chwaszczewski, Ph.D., D.Sc. nuclear power and safety

Andrzej Czachor, Ph.D., D.Sc. solid state physics

Ludwik D ąbrowski, 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


11

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


12

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 Gryzi ński, 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

ANNUAL REPORT 2007 Operation and Safety of Maria Reactor

15

OPERATION OF THE MARIA RESEARCH REACTOR G. Krzysztoszek, A. Gołąb, J. Jaroszewicz

Institute of Atomic Energy

The multipurpose high flux research reactor MARIA is a water and beryllium moderated reactor of a pool type with graphite reflector and pressurized chan-nels containing concentric six-tube assemblies of fuel elements. It has been designed to provide high degree of flexibility. The fuel channels are situated in a matrix containing beryllium blocks and enclosed by lateral

reflector made of graphite blocks in aluminum cans. The MARIA reactor is equipped with vertical channels for irradiation of target materials, a rabbit system for short irradiations and six horizontal neutron beam chan-nels. The main elements of the reactor pool are pre-sented in Fig. 1.

1 2 3 4

5

6

7

8

9

10

11 12 13 14

H3, H8 - 135 cmH7 - 115 cmH4, H5, H6 - 95 cm

+5.0

-1.7

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-tor are as follows:

nominal power 30 MW(th), thermal neutron flux density 4.0·1014 n/cm2s, moderator H2O, beryllium, cooling system channel type, fuel assemblies:

- material UO2-Al alloy

- enrichment 36% - cladding aluminium - shape six concentric tubes - active length 1000 mm.

output thermal neutron flux at horizontal channels 3÷5x109 n/cm2s

The MARIA reactor reached its first criticality in December 1974. The reactor was in operation until 1985

Operation and Safety of Maria Reactor ANNUAL REPORT 2007

16

when it was shut down for modernization. The mod-ernization encompassed refurbishment and upgrading of technological systems. In particular, the efficiency of ventilation and cooling systems was improved. In 1993 the MARIA reactor was put into operation again.

The main areas of reactor application are: - production of radioisotopes, - testing of fuel and structural materials for nuclear

power engineering, - neutron radiography, - neutron activation analysis, - neutron transmutation doping, - research in neutron physics.

In 2007 the reactor completed 40 operation cycles at power levels from 30 kW to 20 MW (Fig. 2). The overall operation time was 4002 h.

The main activities carried out in MARIA reactor were focused on:

- irradiation of target materials in vertical channels and in rabbit system,

- neutron scattering experiments using neutron beams from reactor horizontal channel,

- neutron radiography research at the horizontal channel H8,

- neutron modification of crystals and minerals.

At present only MR-6 type fuel assemblies with 36% enrichment and 430g contents of U-235 are loaded in the reactor core. The release of fission products from this fuel is very low and achievable burn-up is above 50%.

The core configuration has been changed several times because of fuel and irradiation requirements. The core configuration of December 2007 (Fig.3) consisting of 17 fuel assemblies-main core and 7 fuel assemblies in the lateral row was due to the needs of irradiation of minerals under special neutron flux conditions.

Fig. 2. Schedule of the reactor MARIA operation in 2007.


17

Fig. 3. Core configuration of December 2007.

364 spent fuel assemblies have been collected dur-ing many years of reactor operation. The assemblies have been stored under water in the special pool adja-cent to the reactor pool. To prevent possible damage of fuel cladding due to the corrosion processes the assem-blies are encapsulated in special tight cans filled with inert gas. The encapsulation technology was developed and implemented in 2002. Until the end of 2007 157 fuel assemblies were closed successfully in cans made of stainless steel.

The removal of the encapsulated fuel assemblies from the reactor fuel storage has been initiated on De-cember 2005. Until the end of 2007 96 encapsulated fuel assemblies were removed from the reactor storage pool to the temporary wet spent fuel storage.

In 2007 the MARIA reactor was operated success-fully. Nevertheless the reactor scram was activated 11 times. Nine times the reactor was shut down only for a very short time, mainly for the reason of drops in elec-trical power supply system and malfunction of the reac-tor instrumentation system. Two reactor scrams caused shortening of the operation cycles: - first due to a leakage in the primary cooling system, - second due to malfunction of transducer in the main

pump supplying system.

Operational availability factors were:

%7.98%1001 =⋅=NH

OTA

%7.45%1008760

2 =⋅= OTA

where OT (operational time) denotes the number of hours on power and NH is the sum of number of hours on power and on unscheduled shutdown.

In 2007 the total emissions of radioactive materials to the environment were as follows:

- inert gases (mainly 41Ar): 1.19·1013 Bq, i.e. 1.2% of the limit determined by the NAEA,

- iodine: 1.37·108Bq, i.e. 2,7% of the limit deter-mined by the NAEA,

- 88Rb and 138Cs: 1.87·109 Bq. In 2007 99 workers received measurable whole

body doses from 0.1 to 3.82 mSv and 8 workers re-ceived skin doses from 0.65 to 5.34 mSv.

The electrical conductivity and pH value of water in the main reactor systems were controlled perma-nently (Fig. 4, 5).


18

0

1

2

3

4

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

Con

duct

ivity

mS

/cm

Inventory tank Fuel channels Storage pool Reactor pool

Fig. 4. Conductivity of water in the primary circuits of the reactor Maria in 2007.

4,5

5,5

6,5

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

pH v

alue

Inventory tank Fuel channels

Storage pool Reactor pool

Fig. 5. pH value of water in the primary circuits of the reactor Maria in 2007.

New technology - neutron irradiation services

Neutron irradiation services utilizing MARIA research reactor include radioisotope production, neutron trans-mutation doping of silicon, neutron activation analyses and biomedical technology.

Available services cover the activation of a large variety of target materials for the production of isotopes which would subsequently be processed at the discre-tion of the customer. For irradiation services various systems are available in the MARIA reactor, providing necessary irradiation conditions according to the re-

quired neutron flux levels, irradiation times, target mass and size.

The vertical in-core isotope channels were consid-ered as a design requirements for high activity radioiso-topes production as well as the modernized hydraulic transfer system. For the domestic customers the targets of S, TeO2, Lu2O3, Yb2O3, Cu, Se, SmCl3 and KCl were irradiated (Fig. 6).

Most of the radioisotopes were produced for the Isotope Research and Development Center POLATOM. Among the new approaches developed for radioisotopes of current interest in nuclear medicine and industry were


19

iridium seed-targets. The source wire in each seed was made of platinum - iridium alloy. The Ir-192 seeds used in Intravascular Radiation Therapy (IRT) and low activ-ity Ir-192 ribbon for oncology applications were pro-duced.

The irradiation services offered at MARIA re-search reactor include the Neutron Transmutation Dop-ing (NTD) of silicon crystals. High purity silicon single crystals are doped to produce n-type semiconductor material. The NTD is based on the transmutation of 30Si atoms into 31Si by the capture of thermal neutrons. The 31Si decays by the emission of beta particles to 31P. The results of experimental irradiation of silicon ingots of 5” and 6” diameter confirmed good quality of neutron doped silicon crystals. The uniform neutron dose distri-bution over the ingot ensures the homogeneous distribu-tion of phosphorous atoms throughout the silicon crys-tal, resulting in uniformly doped n-type silicon matching the electrical resistivity needed. The axial and radial resistivity variation of the sample is controlled to satisfy the customer needs. At present the facility installed in the poolside region of the reactor is ready for commer-cial neutron transmutation doping of silicon ingots for 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.

Neutron irradiation service utilizing reactor MARIA includes the coloring of topaz minerals. The irradiation of minerals in special channels located out-side reactor core change its colorless transparent natural state to shades of blue, thereby increasing the commer-cial value of the product. After appropriate cooling time the blue minerals are released to the market as the non-radioactive material.

Feasibility study on irradiation of 235U targets in the MARIA reactor for 99Mo production has been started in 2007. The main objective is to obtain the 99mTc isotope, which is widely used in the medical diag-nostics. The decisive factor determining its availability, despite its short life time, is the radioactive decay of 99Mo into 99mTc. One of the possible sources of molyb-denum can be achieved within the 235U fission reaction. Currently 99Mo is produced by most producers by irra-diation of HEU targets. The new idea that conforms to the Reduced Enrichment for Research on Test Reactors (RERTR) program is to use LEU-foil targets. Technol-ogy for production of 99Mo is based on the core loop which consists of standard fuel channel supplemented with necessary control units.

0

100

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300

400

500

600

700

800

900

1000

1100

1200

1978

1979

1980

1981

1982

1983

1984

1985

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1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

2004

2005

2006

2007

Year

Num

ber

of th

e co

ntai

ners

irra

diat

ed otherbiological materialslutetiummineralspotasium chloridexenoniridiumcobaltmolibdenumtelluriumsamariumsulphur

Fig. 6. Distribution of target materials irradiated.


20

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-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 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 been extended.

The present model accounts for: − initial fuel element material composition given in

fuel certificates, − individual fuel element burnup history, − 15 types of geometry of beryllium blocks, − individual beryllium block transmutation history, − special purpose channels and blocks including

irradiation channel, − control and safety rods with their operational posi-

tions in 3D calculations, − core reflectors.

The computations are performed using current data on the core configuration, reactor power, control rods position and materials temperatures.

Computational results are routinely compared to the measured data on reactivity change with fuel burnup and transmutations in beryllium (weekly and annually), control rod worth, temperature reactivity coefficients.

The analysis of the burnup level of particular fuel elements [2] resulted in the corrections of geometrical representation of irradiation channels and absorbing filters. Without corrections marked differences between the calculated and measured burnup level are observed (Fig. 1). The corrections improved the compatibility of the calculation results of the new model with the meas-ured fuel burnup of fuel elements (Fig. 2).

Further analysis carried out together with Argonne National Laboratory [3] under the RERTR cooperation, has shown the effects of: − application of burnup dependent library of REBUS

for MARIA fuel elements gives improvement of about 2% in keff,

− introduction of axially dependent burnup gives up to 1% improvement in keff.

0

500

1000

1500

0 500 1000 1500

Energia REBUS [MWh]

En

erg

ia p

om

iar

[MW

h] .

Calculated burn-up [MWh]

Mea

sure

dbu

rn-u

p[M

Wh]

0

500

1000

1500

0 500 1000 1500

Energia REBUS [MWh]

En

erg

ia p

om

iar

[MW

h] .


Mea

sure

dbu

rn-u

p[M

Wh]

Fig. 1. Calculated vs. measured burn-up level of fuel elements,

old model. Light green points correspond to fuel chan-nels neighboring to isotope channels, dark green – close to absorbing filters, green – the others.

0

500

1000

1500

0 500 1000 1500

Energia REBUS [MWh]

En

erg

ia p

om

iar

[MW

h] .


Mea

sure

dbu

rn-u

p[M

Wh]

0

500

1000

1500

0 500 1000 1500

Energia REBUS [MWh]

En

erg

ia p

om

iar

[MW

h] .


Mea

sure

dbu

rn-u

p[M

Wh]

Fig. 2. Calculated vs. measured burn-up level of fuel elements,

new model. The description of points is the same as in Fig. 1.

Three new auxiliary programs [4] have been devel-oped to facilitate REBUS input preparation.

The computational model has been used in predic-tion of the reactivity change of planned beryllium blocks reloading. Block from position I-VII is going to be exchanged with that at K-IX, and H-VII with that at K-V.

References [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)

ANNUAL REPORT 2007 Radiation Protection and Dosimetry

23

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-tory (RPML) of the Institute of Atomic Energy is re-sponsible for handling all the problems concerning radiation protection at the Institute and in the vicinity of Nuclear Centre (NC) Świerk and National Repository of Radioactive Waste (NRRW) at RóŜan.

The main tasks of RPML are: - Radiation monitoring of the Świerk and RóŜan

sites. - Surveillance of radiation safety. - Radioactive waste control. - Radiation protection in emergency conditions. - Improvement of radiation protection measurements

and methods. - Calibration of radiation protection monitoring in-

struments. - Personal dosimetry. - Sewage and drainage water activity measurements. - Environmental radiation monitoring.

The following laboratories and facilities are avail-able in the Laboratory: - Mixed radiation fields laboratory (MRF). - Whole body counter (WBC). - Counter of thyroid activity (TC). - Calibration laboratory with standard radiation

sources (Calibration Division, CD). - Environmental measurements laboratory. - Radiochemical laboratory (RL).

On December 31, 2007 the Laboratory employed 19 graduate staff members and 9 non graduated.

In 2007 RPML continued successfully the activi-ties concerning improvement of measurement proce-dures in two main domains of Laboratory accredited by the Polish Centre for Accreditation (PCA): - The determination of internal body contamination

(whole body, thyroid and excretions) – accreditation No. AB 567.

- Calibration of dosimetric instruments (gamma, neutron and surface contamination monitors) – ac-creditation No. AP 070.

The improved versions of Quality Manual as well as all the procedures were completed and some techni-cal and organizational activities undertaken, especially concerning validation, traceability and estimation of uncertainties of the methods used.

Several internal quality audits were performed, opinions collected from experts, and in March 2007 the yearly PCA audit took place for AB 567 and in Septem-ber 2007 for AP 070, both with positive results.

The research activities of Laboratory are described on the next pages of the Annual Report.

The technical activities of the RPML in 2007: - Whole body (WBC), thyroid (TC) and “in vitro”

(RL) monitoring were carried out for radiation workers from NC Świerk and external customers: 392 WBC, 161 TC and 170 RL measurements were made in 2007 (Tables 1- 3). The collected results of measurements of 137Cs internal activity in people, from 1986 and 2007, are presented in Fig. 1.

- Regular monitoring of radiation workers was car-ried out with TLD dose meters. Values of individual dose equivalents registered are below the annual dose limit.

- The environmental monitoring within or outside the NC and NRRW boundaries included the measure-ments of direct or stray radiation due to the opera-tion of reactors, accelerators, etc. and the measure-ment of radioactivity in samples of air, rivers’ and underground water, soil, sediment, mud and vegeta-tion. In 2007 more then 1000 environmental sam-ples were measured (Tables 4-6).

Table 1. Whole body counter measurements.

Dose measurements persons

< 1% EW 392 282*

> 1% EW - -

Total 392 282

* - 37 persons were contaminated by iodine 131 including 19 per-sons measured by Thyroid Counter and calculated the committed dose equivalent.

Ew – limit of annual effective dose.

Table 2. Thyroid counter measurements.

Dose

Measurements Persons < 1% EW > 1% EW

Total 161 32 24 8

Table 3. Measurements of biological probes.

Measure- ments

Persons <1% EW >1% EW

Total α-activity 2 2 2 -

Total β-activity 126 103 103 -

Activity of P-32 9 6 6 -

Activity of S-35 7 5 5 - Activity of tritium (HTO) 23 19 19 -

Activity of Sr-90 3 3 3 -

The results of performed measurements indicate that there is no contamination of the environment and the human population in the vicinity of the NC and NRRW.

Radiation Protection and Dosimetry ANNUAL REPORT 2007

24

0

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tal b

od

y ac

tivi

ty f

rom

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3

Woman

Men

LDA

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.

Concentration [Bq/dm3] Average value min max medium

Type of probe and place of collection

Number 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.

Average value Concentration of trytium [Bq/dm3] Type of probe and place of collection

Number of 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 Outside of NRRW RÓśAN

F-1 24 10 36 42 27

Tap water (inside NRRW) F-R < 4,0 < 4,0 < 4,0 26 < 4,0


25

Table 6. Activity of environmental samples (soil and grass) from inside and outside the NRRW RóŜan in 2007 [Bq/kg].

Place K-40 Cs-137 Ac-228 Ra-226 Type of probe

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-

ing the standard fields of neutron and gamma radiation. The 137Cs is the main calibration source of gamma ra-diation. Standard neutron fields, traceable to primary standard laboratory National Physical Laboratory (NPL, Great Britain) were established at the Institute of Atomic Energy (IAE) ten years ago. The fields are formed by calibrated sources of 252Cf and 241Am-Be. For routine use, there is also 239Pu-Be neutron source avail-able calibrated against standard source of 241Am-Be. Additionally, spherical filters made of iron or paraffin can be applied for modification of the neutron spectrum and gamma component of absorbed dose.

The neutron sources are used mostly for research purposes. However, since they form the only standard neutron fields in Poland, they are employed for calibra-tion of neutron dose meters used in radiation protection. Maintenance of the fields includes periodic assessment 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.

Calibration Laboratory performs calibrations of surface contamination monitors, using reference sources of beta and alpha radiation. In 2007 a new standard source 36Cl for contamination monitors was introduced for routine use.

Total number of monitors calibrated in 2007 was: - Surface contamination monitors - 107 - Gamma dose and dose rate monitors - 150 - Neutron dose equivalent monitors - 7

In 2007 the staff of CD performed the periodical tests of dosimetric monitoring system of MARIA reac-tor as well as the calibration of data lines of the system with the detectors.

The calibration of radiation monitors in liquid ra-dioactive waste storage tanks of Radioactive Waste Management Plant was performed as well as the calibra-tion of radiation monitoring personal gate.


26

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-encing the ion collection efficiency in high pressure ionization chambers – initial recombination and volume recombination.

Initial recombination occurs between oppositely charged ions from the same track of a charged particle. It dominates at gas densities of several kg/m3, electrical field strength above 1 kV/m and the absorbed dose rate in the gas below ca. 1 Gy/h.

Volume recombination occurs between ions from different tracks formed by ionizing particles. It depends on the measured current, i, hence on the absorbed dose rate in the gas cavity. It is independent neither of LET, ionization particle energy nor of other parameters de-scribing the radiation quality. This kind of recombina-tion is a dominant process of ion recombination at high dose rates, in ionization chambers with large distance between electrodes and at low gas density. The cham-bers with smaller distance between electrodes can oper-ate at higher dose rates, or at lower voltages.

Initial recombination occurs in very short time after formation of the charged particle track, until the ions diffuse to the distance of few hundreds nanometers. The volume recombination is present all the time of ion collection in the chamber. The initial and volume re-combination are the consecutive processes, i.e. the ions that recombine through volume recombination are those which have avoided the initial recombination.

The ion collection efficiency in an ionization chamber can be expressed as the ptoduct:

kvi ffff ⋅⋅=

where fi and fv are ion collection efficiencies of local and volume recombination, respectively, fk is the correc-tion factor for other effects including back diffusion of ions, radiation background, leakage current, and temperature effects.

For steady radiation and given polarizing voltage U, the ion collection efficiency in the volume recombi-nation process, fvs , can be expressed as [2]:

2/1

1

Uiaf

vvs

+=

For pulse radiation, the ion collection efficiency fvp , can be approximated by similar formula:

Uibf

vvp /1

1

+=

Both coefficients, av and bv, depend on the distance between electrodes in the chamber and the gas parame-ters. For given ionization chamber, av and bv are con-stant. The coefficient av can be determined from the measurements of ion collection efficiency at different dose rates in a steady radiation field [3]. Similar proce-dure can be performed in order to determine the con-stant bv in a pulse radiation field.

In the case of quasi-pulsed fields when the ion col-lection time and the pulse repetition time are of the same order of magnitude or when both the steady and the pulse components are present none of the above equations is correct.

In our approach [4], we assume that the ion collec-tion efficiency in the volume recombination process, has the form

( )UFif v /1

1

+=

where F(U) is an unknown function of the voltage U.

Then, the ion collection efficiency f(U) should be determined for two different dose rates of investigated radiation, without changing its time structure. The dose rates should grant the negligible volume recombination at highest voltage applied to the chamber. Combining the first and the last of the above equations, one can get two equations for two values of i, with two parameters – F and fi to be calculated, for each voltage U. No detailed information is needed about the time structure of radia-tion.

References [1] N. Golnik, Raport IAE–20/A (1996) [2] J.W. Boag, in: Attix, F. M. Roesch, W. C. (eds.), Radia-

tion dosimetry, II , Acad. Press, (1968) [3] M.A. Gryziński et al., Nukleonika, 52(1) 7 (2007) [4] N. Golnik et al., Nucl. Instr. and Meth. A 580 25 (2007)


27

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 (versus reference gamma radiation) was determined from the measurements of saturation current in almost monoenergetic neutron fields with energies ranging from 75 keV to 19 MeV. The measurements were per-formed in the low-scatter environment of the Physi-kalisch Technische Bundesanstalt (PTB, Braunschweig, Germany) accelerator facility [1]. A De Pangher preci-sion long counter and a 3He detector served as neutron monitors. In addition, the beam charge collected on the target was continuously monitored.

The REM-2 chamber was positioned at a distance of 2.5 m from the target. The reading of the chamber was normalized to the beam charge.

The photon dose fraction of the mixed neu-tron/photon fields was determined with a Geiger-Müller (GM) counter (type ZP1100). The photon contribution to the absorbed dose was below 2% for all neutron fields with nominal energies greater than 0.6 MeV.

The measurements in high-energy neutron fields were performed at CERF facility in CERN. The beam, of 120 GeV/c positively charged particles (protons and pions extracted from the SPS accelerator) was directed onto a copper target. The target was placed either in the position under a 40 cm thick iron roof shield (called iron position) or under an 80 cm thick concrete roof shield (called concrete position). The beam was shielded from the side by a concrete wall with the thickness of 80 cm for the concrete position and of 160 cm for the iron position. The time characteristic of the field revealed the pulse structure of the beam with the duration time of 2 s and repetition time of 14.4 s. Beam intensity was moni-tored with a Precision Ionization Chamber (PIC) in the beam line located at the end of the beam pipe upstream of the target positions. The reference values of H*(10) are based on calculations and evaluated results of the intercomparisons [2].

Measurements were performed also in frame of the EURADOS benchmark experiment at Gesellschaft für Schwerionenforschung (GSI, Darmstadt, Germany). Beam of 12C ions with a specific energy of 400 MeV/u and intensity of 2·109 ions per spill was delivered by the heavy-ion synchrotron SIS-18 to the experimental area 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.

0.1 1 10 1000.0

0.5

1.0

1.5

2.0

h

E [MeV]

Fig. 1. Dependence of the relative neutron sensitivity to D*(10) on neutron energy, for REM-2 chamber.

We found [4] that the REM-2 chamber calibrated with the 137Cs source, overestimates the D*(10) values for neutrons of 0.05-4 MeV and in high energy region (Fig. 1). The effect at lower energies is due to higher content of hydrogen in the gas in the chamber than it is in tissue. The influence of the gas composition becomes less important at higher energies and the overestimation is caused mainly by higher contents of carbon and lower content of oxygen in tissue equivalent material, com-pared to tissue.

At the energies around 14 MeV, there is a narrow minimum in the relative neutron sensitivity of the chamber. The lowest value of h = 0.76 was recorded for 14.8 MeV neutrons but the range of neutron energies where h is considerably below 1 is narrow and the influ-ence of the region on the results of the measurements in high energy radiation fields is usually very small or negligible.

References [1] H. J. Brede et al., Nucl. Instrum. and Meth., 169 349

(1980) [2] M. Höfert, G. R. Stevenson, Report CERN/TIS-

RP/IR/94-02, CERN, Geneva, 1994 [3] H. Iwase et al., Radiat. Prot. Dosim., 116 640 (2005) [4] N. Golnik, M. Zielczyński, IEEE Nuclear Science Sym-

posium and Medical Imaging Conference, Honolulu, Hawaii, USA, October 27 – November 3, 2007, N39-3


28

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 131I radiation spectrum registered by NaI(Tl) detector during measurement of iodine 131I source immersed in the water thyroid phantom.

The calculations were carried out for the thyroid phantom used in Radiation Protection Measurements Laboratory for thyroid counter calibration. The thyroid location inside the phantom can be altered in vertical and horizontal plane [1]. The results of the 131I radiation spectrum simulation can serve as an assessment of the implementation of changes into the testing equipment.

Our calculations were performed with the Monte Carlo “Penelope” code using the appropriate modifica-tion of “Penmain” program [2]. The modelled detector consists of cylindrical scintillator plate (40 mm diame-ter, 25 mm height) contained within 1 mm thick alumin-ium sheath (46 mm diameter, 32 mm height). The space between the scintillator and the wall is filled with Al2O3 powder. Detector is sheltered with the cone shaped lead collimator. The spherical 131I source was placed in cyl-inder which was modelled as tissue and water. The results of measurements of iodine source in the water thyroid phantom and in the human neck should be com-parable.

1 25 49 73 97 121

145

169

193

217

241

265

289

313

337

361

385 S10,00E+00

5,00E-09

1,00E-08

1,50E-08

2,00E-08

2,50E-08

Fig. 1. The iodine 131I spectrum for thyroid depth 23 mm –

measured (upper) and calculated (lower).

The calculated and measured radiation spectra for 23 mm thyroid depth are similar except the height of the 30 keV energy peak (Fig. 1). Since this part of spectrum is not used in determination of the iodine activity, the difference is not of practical importance.

The method for calibration of the thyroid counter with 131I used in Radiation Protection Measurements Laboratory takes into account the position of the thyroid inside human neck. The thyroid depth is determined using parameter S defined as the ratio of the 364 keV counts and number of counts in the spectrum region of Compton scattering photons. This region is 100-150 keV (S1) or 110-140 keV (S2). The results of the calibration process are two curves: values of the pa-rameter S versus the thyroid depth and values of detec-tion efficiency versus parameter S [1].

The Monte Carlo calculations were carried out for six different values of thyroid depth. The calculated S1 and S2 parameters agree to those determined experimen-tally (Fig. 2).

0

0,5

1

1,5

2

2,5

20 30 40 50 60 70 80

thyroid depth [mm]

S

Experimental

Calc. - tissue

Calc. - water

Fig. 2. The values of parameter S1 (lower curve) and S2 (upper curve) versus thyroid depth determined from measure-ments and calculations results.

Our results indicate that the Monte Carlo model can be used for pre-calibration research and the water thyroid phantom is a good model for the gamma ray absorption and scattering in human neck.

References

[1] J. Ośko et al., Raport IAE-122/A (2005) [2] F. Salvat et al., Penelope-2006, Workshop Proc., 4-7

July 2006, Barcelona, Spain


29

RELATIVE NEUTRON SENSITIVITY OF IONIZATION CHAMBER FILLED WITH HYDROCARBON GASES

M.A. Gryzi ński 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 An = in(US) / nD& is the sensitivity of the chamber

to neutrons with spectrum considered; D& ≡ D*(10) is the ambient absorbed dose rate at the point of measure-

ment; and AC = iC(US) / CD& is the sensitivity to the

reference gamma radiation (137Cs source). in(US) and iC(US) are ionization currents in neutron radiation field and in the reference gamma radiation field measured at the voltage US respectively.

The value of relative sensitivity hn is necessary when the chamber is used for the determination of the dose components in mixed (neutron + gamma) radiation field, using the twin-chambers techniques. The second chamber is usually a hydrogen-free chamber with low relative sensitivity to neutrons. The dependence of hn on gas density was determined [1] using reference radiation fields of 137Cs and 239Pu-Be sources and subtracting the earlier known contribution of gamma radiation from the Pu-Be source.

The recombination chamber of REM-2 type with tissue equivalent electrodes was used in the studies. The chamber of ~1800 cm3 volume and the distance d = 7 mm between electrodes was employed. The measure-ments were performed with the chamber filled with methane, ethane, ethylene or propane up to the pressure of 1.8 MPa. The results are presented in the form of the hn dependence on gas density instead of gas pressure (Fig. 1).

Fig. 1. Dependence of the relative neutron sensitivity (neu-trons from 238Pu-Be source) of the REM-2 chamber on filling gas density for methane (the upper curve) and propane (the lower curve).

The gases with high content of hydrogen (CH4) are most convenient for the high pressure recombination chambers used in mixed radiation fields, because with such gases it is easier to obtain similar sensitivity of the chamber to neutron and gamma radiations. However, it is not possible to have hn ≈ 1 for all neutron energies. For the REM-2 chamber filled with methane (p = 1 MPa, US = 1200 V) the hn changes from 0.6 up to 1.5 in the neutron energy range from thermal to 200 MeV. However, in the case of the radiation of un-known neutron energy, it is preferable to have hn less energy dependent, even if the value of hn considerably differs from unity.

The maximum observed in the dependence of hn on the gas density (Fig.1) is caused by increasing contribu-tion of directly ionizing particles created in gas to the ionization current, with increasing gas density. The decrease of hn with increasing density observed at higher gas densities is due to the initial recombination of ions in tracks formed by ionizing particles produced by neutrons.

References [1] M.A. Gryziński et al., Nukleonika 52 7 (2007)


30

RELATIVE LOCAL IONIZATION DENSITY – CORRELATIONS WITH MICRODOSIMETRIC PARAMETERS

M. Zielczyński, N. Golnik Institute of Atomic Energy

Local recombination of ions is the recombination which occurs within a column or group of ions created by one charged particle. This type of recombination occurs a short time after the primary ionization events, before the ion column spreads out due to the diffusion and ion drift in the electrical field in the detector. The volume recombination may take place afterwards. Local recombination of ions does not depend on the dose rate but it does depend on local ionization density in the track of the charged particle, thus it depends on LET, it can therefore be used for determination of the radiation quality factor. It was shown [1] that the ion collection efficiency, f, of the ionization chamber with the local recombination, defined as the ratio of the ionization current at a given polarizing voltage to the saturation current, can be described by simplified formula:

Cs

Cs

f

ff −⋅+

=1

1

1

µ

where µ is the relative local ion density of the consid-ered charged particles, defined in such a way that µ = 1 for gamma radiation in a reference radiation field of 137Cs under conditions of initial recombination, while ion collection efficiency in this field is fCs . The f and fCs have to be determined at the same polarizing voltage.

Although the parameter µ has not clear physical meaning it is measurable quantity defined as:

Cs

Cs

f

f

f

f

−⋅−=1

1µ

The parameter µ is constant for given radiation for the ionization chamber filled with pressurized gas at a definite range of density. Therefore, it is considered as a physical parameter which characterizes the radiation quality.

In different theories of ionization energy deposi-tion, the value of µ can be used as approximations of the following quantities [2]:

1. Ratio of the linear ionization density υ, of the con-sidered ionizing particles to the mean linear ioniza-tion density of the standard gamma radiation υCs :

Csυυµ =

The equation can be used at υ ≥ υCs ≈ 100 ion pairs/µm H2O.

2. Ratio of the mean lineal energies:

( )Csd

d

y

y=µ

The mean chord of the site, d, is in this case of about 25 nm, what corresponds to a sphere diameter of about 0.15 µm. The dose mean lineal energy for 137Cs gamma radiation is about 5 keV/µm.

3. Ratio of the effective restricted LET of the consid-ered particles and the reference radiation:

( )CsL

L

∆

∆=µ

with the cut-off ∆ ≈ 500 eV or ∆ ≈ 70 nm if the cut-off is expressed in units of length. Effective restricted LET means here the mean value of restricted LET weighted by the transferred energy, taking into account the pri-mary particle and delta electrons with energy Eδ > ∆, which are considered as the separate particles associated with the primary ones.

4. Ratio of unrestricted LET of the considered parti-cles and of the reference radiation:

µ = L / L0 for L ≥ L0 ≡ LCs = 3.5 keV/µ

µ = 0.85 + 0.15 L / L0 for L < L0

5. Ratio of the numbers of ion pairs generated in a micro-site with the mass of about 1 fg crossed by a particle track in the radiation fields of the consid-ered and reference radiations:

Csv

v=µ

6. Ratio of the proximity function T(x) for the consid-ered and reference radiations.

CsxT

xT

)(

)(=µ

at x = 70 nm.

The equations given above may yield somewhat different values of µ for the same, well defined radiation but within inaccuracy range of about 10%, which is usually acceptable in radiation protection. In radiation fields of unknown composition, µ can be determined experimentally using a recombination chamber.

References [1] N. Golnik, Raport IAE–20/A (1996) [2] M. Zielczyński et al., IAE Report B-10 (2007)

ANNUAL REPORT 2007 Radiation Protection and Dosiometry

31

RADIATION FIELDS OF GAMMA IRRADIATOR IN CALIBRATION ROOM OF RADIATION PROTECTION MEASUREMENTS

LABORATORY K. Józefowicz, B. Boimski, P. Tulik, M. Zielczyński


In calibration hall of Radiation Protection Meas-urements Laboratory (LPD) a new gamma irradiator [1] for calibration of dosimetric instruments has been in-stalled within a PHARE program PL2002/000-632.07.01. The computer operated irradiator contains 137Cs, 60Co and 241Am sources, recommended by Inter-national Standard Organisation (ISO) for calibration of dosimetric instruments [2]. The sources are stored inside the heavy shield container and the pneumatic system is used to transport a source into working position in a collimator. Computer program is applied to choose a source and to establish the mode of irradiation.

Fig. 1. Gamma irradiator.

An extensive work has been performed to determine the dosimetric parameters of the gamma fields produced by irradiator [3]. Standard fields of gamma radiation in LPD are traceable to Central 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, using secondary standard ionisation chamber. Accord-ing to the GUM certificates, the air kerma rate at distance 1 m on 31 December 2007 was equal to (29.39 ± 0.28) mGyh-1 for 137Cs and (2.834 ± 0.028) mGyh-1 for 60Co. From the results of the GUM measurements, the tables and graphs of air kerma rate and ambient dose equivalent rate dependence on the 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.

To determine the gamma field of 241Am, emitting 60 keV gamma rays, two chambers of flat energy de-pendence, Robotron VAJ with air chamber [4], and ionization chamber KG-2, developed in IAE [5], have been applied. The air kerma rate determined with Ro-botron chamber at 1 m distance is (20 ± 1) µGy h-1 (Fig.2). To dependence the air kerma rate on the dis-tance from the source was determined with the KG-2 chamber. The full account of the results is given in [3].

0.00

10.00

20.00

30.00

40.00

50.00

60.00

0 0.5 1 1.5 2 2.5 3

distance, [m]

kerm

a ra

te [ µ

Gy/

h] a

nd d

ose

eq. r

ate

[ µS

v/h]

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 of the gamma calibrations to three energies; with higher dose rates available. The whole set of gamma field sources assembled in the calibration hall of Laboratory, provides an important tool for calibrations of radiation protection instruments and experiments with new de-vices.

References [1] Source calibrator irradiator mod. IM6/M. Instruction

and service handbook (Rev. 1.0 05/05). Tema Sinergie s.r.l.

[2] ISO-4037-3: 1999 [3] K. Józefowicz et al., IAE Report B-14 (2007) [4] Röntgen-Gamma Dosimeter 27 040 – Technische Be-

schreibung und Bedienungsanleitung VEB Robotron-Messelektronik “Otto Schön” Dresden (1987)

[5] M. Zielczyński, N. Golnik, Monografie IEA 3 81 (2000)

ANNUAL REPORT 2007 Nuclear Technology in Energy Generation

35

STAND AT THE MARIA RESEARCH REACTOR FOR THE STUDIES OF TRANSMUTATION OF FISSION PRODUCT S

AND INCINERATION OF MINOR ACTINIDES S. Kilim1, E. Strugalska-Gola1, M. Szuta1, A. Wojciechowski1, Z.Woźnicki 1, 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-tion of radioactive long-lived fission products such as 99Tc, 129I and 135Cs and by incineration of minor acti-nides is a very large field of study requiring significant experimental and financial support.

We propose to replace the accelerator spallation source with the neutron source obtained by converting the thermal neutrons from the horizontal channel of the research reactor MARIA into fast neutrons. Taking into account the large flux of thermal neutrons in the hori-zontal channel, it is possible to use a fission converter i.e. an arrangement containing 235U placed in the axis of the horizontal beam. Thermal neutrons cause the fission reactions producing fast neutrons needed.

A natural metallic uranium blanket covering sev-eral fuel rods of EK-10 type constitutes the converter to be placed on the moderator support (Fig. 1). The space between the EK-10 type fuel rods will be filled with lead which does not moderate the fission fast neutrons. A polyethylene blanket covering the fuel rods has been also considered.

Fig. 1. The simplified converter geometry of the stand.

The converter (Fig. 1) consists of two zones: first the fast neutrons zone consisting of EK-10 type fuel

rods placed in the lead block and the second, thermal neutron zone consisting of metallic natural uranium rods (NH3) placed inside the polyethylene block. The natural uranium rods of 30 cm length, 2.72 cm diameter and 2.8735 kg weight are hermetically sealed in an alumin-ium cladding.

The sub-critical calculations for the stand at the horizontal channel of the MARIA research reactor have been performed using Monte Carlo N-Particle method-ology of version MCN PX. The calculations were nor-malized to one external neutron source. The axial distri-bution of total neutron flux in the experimental channels of the lead support were calculated (Fig. 2).

For the thermal neutron flux of 3 – 5·109 cm-2s-1

at horizontal channel we obtained the total neutron flux in the first channel (d=15 cm) equal to ~5·10 6 cm-2 ⋅s-1 and for the fifth (d=115 cm) ~103 cm-2 ⋅s-1.

-80 -40 0 40 80

1E-7

1E-6

1E-5

1E-4

1E-3

1E-2

z [cm]

Tot

al n

eutr

on fl

ux [1

/cm

2]

Neutron flux in channelat position (x,y)[cm]

(0, -15)

(0, -50)

(0, -65)

(0, -95)

(0, -115)

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. References [1] S. Kilim et al., IAE Report B-41 (2007)

Nuclear Technology in Energy Generation ANNUAL REPORT 2007

36

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

The neutron field inside the U/Pb assembly of the JINR Dubna experimental set-up ‘Energy plus Trans-mutation’ (EpT) was investigated with the Y-89 activa-tion detectors. In the experiment the 1.6 GeV deuteron beam impinged on the cylindrical lead target surrounded by uranium blanket shielded by polyethylene container [1,2]. The neutron field was determined with thirty five pure Yttrium 89 (99.9% Y-89) samples placed in speci-fied positions inside the U/Pb assembly. Neutron captu-re in Y-89 yields various (n,xnyp), reactions, where ‘x’ and ‘y’ are integer numbers. Isotopes created in these reactions are unstable and gamma active. After the 5.8 × 1013 beam deuterons were collected the gamma activity was measured with HPGe spectrometer. Taking into account necessary corrections we have determined iso-tope production per one gram of the sample and per one beam deuteron at specified positions inside the EpT facility. The spatial distribution of the Y-88 isotope production was determined (Fig. 1). The presence of the Y-87 and Y-86 was also revealed.

0,0E+002,0E-054,0E-056,0E-058,0E-051,0E-041,2E-041,4E-041,6E-041,8E-04

B[n

ucl

ei/g

/deu

tero

n]

0.03.06.08.510.513.5

0.0 11.8 24.0 36.2 48.4

Radius[cm

]

Axial position [cm]

1.6 GeV deuteron beam

Fig. 1. Spatial distribution of Y-88 produced by spallation neutrons in Y89(n, 2n) reaction.

The spatial distribution of the Y-88 isotope (Fig. 1) is a superposition of two processes – beam deuteron interaction with the samples and spallation neutron interaction. During the deuteron interaction with yttrium 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. 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).

1.6 GeV deuteron beam

0,0E+00

1,0E-05

2,0E-05

3,0E-05

4,0E-05

5,0E-05

6,0E-05

7,0E-05

0.0 11.8 24.0 36.2 48.4

Position along the target [cm]B

[nu

clei

/g/d

eute

ron

]

Y88 S2

Y87 S2

Y86 S1

Fig. 2. Axial distribution of isotopes produced at radial di-stance 3 cm from the 1.6 GeV deuteron beam axis by spallation neutrons in Y89(n,xn) reactions.

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 production ratio (e.g. Y87/Y88) depends on neutron energy spectrum and can serve as a spectral index. The region of constant spectral index (SI) was found in the middle of the EpT assembly (Fig. 3).

0,0

0,1

0,2

0,3

0,4

0,5

0,6

0,7

0,8

0,9

0.0 11.8 24.0 36.2 48.4

Position along the target [cm]

SI

Y87/Y88

Y86/Y88

Fig. 3. Axial distribution of the spectral index at radial dis-

tance 3 cm from the 1.6 GeV deuteron beam axis.

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)


37

UO2 GRAIN SUBDIVISION FOR VERY DEEP BURN-UP AND RELATIVELY LOW TEMPERATURE

AND ITS IMPACT ON FISSION GAS RELEASE M. Szuta


The beginning of the grain subdivision process in the nuclear fuel is observed at burn-up from ~60 MWd/kgU to 75 MWd/kgU [1] at the temperatures less than 1200 oC. The peripheral region of the high burn-up UO2 fuel rod with a particular nano-structure is known as the “rim region”. The nano-structure changes start when the average burn-up exceeds ~40 MWd/kgU. The marked decrease in the grain size is accompanied by an increase in porosity and a decrease in the signal for fission xenon [2].

It was established [1] that the local xenon concen-tration in the UO2 matrix attains a maximum as a func-tion of the local burn-up. Coincident with the local xenon concentration decrease is the local grain subdivi-sion in the rim area of the pellet. With increasing grain size, rim structure development rate is suppressed, and the Xe depressions for the large-grained pellets are about half of the value for the standard grain size pellet.

Although the physical details of the process are not fully understood, an attempt has been made to describe these processes by a simple model [3]. It is assumed that beside the modification of the properties of the “ather-mal” rim surface layer of the UO2 fuel pellet by neutron irradiation, the total surface area increases when the local xenon concentration decreases. Further on we assume that the fission gas release from the UO2 fuel during low temperature irradiation depends on the knock-out process of the defect trap model and is pro-portional to the total surface area. The knock-out proc-ess occurs also in the fuel transformed by grain subdivi-sion.

We assume that above a limiting value of fission fluency a more intensive process of irradiation induced chemical interaction occurs. Significant part of fission gas products are chemically bound in the matrix of UO2. It seems to be natural that the chemically bound fission gas atoms can form weak facets. At certain saturation conditions subdivision of the grains can occur and the increase in fission gas products release may be ex-pected.

In the defect trap model the fission gas release (R) is described:

VrSMfgR tr /2= (1)

where S – total surface area, f - fission rate, r– aver-

age fission fragment range, V – volume of the subdi-vided fuel, g2 – constant.

When S r attains V then total surface area stops to increase and the process of poligonization is accom-plished.

Assuming that r = 6 µm we obtain that total surface is equal to about 1.6 103 cm2/cm3. Relative density of the fuel for this total surface area is equal to about 89 % and the porosity is ~11 %. This value is comparable with the experimental porosity data (15 %). Thus we obtain the total surface area of ~9 103 cm2/cm3 for 85 % relative density, which we call the limiting total surface area (Sl).

Our analysis let us postulate that the total surface area of the fuel in the rim region depends on the burn-up b in simple way

)1)(( cb

bplbp eSSSS −−−+= , (2)

with Sbp – total surface area before the process, Sl – limiting total surface area and c - a constant dependent on the grain size.

From the solution of the defect trap model equa-tions for the high burn-up we obtain that the release rate is equal to the birth rate

fMfg itr β=2 (3)

where Mtr is the concentration of gas atoms in the bub-bles, and βi is formation yield of the intermediate gas of the i-th isotope.

In conclusion, the increase of gas concentration in function of burn-up is explained by defect trap model and the gas concentration at high burn-up (>120 GWd/tU) does not change. Nevertheless, the behavior of gas concentration in the intermediate burn-up range of 60 – 120 GWd/tU requires further study.

References [1] K. Lassmann, et.al., J. Nucl. Mater. 226 1 (1995) [2] I.L.F. Rayet.al., J. Nucl. Mater. 245 115 (1997) [3] M. Szuta, IAE Report B-45 (2007)


38

ADVANCES IN THE SUB-CRITICAL MC CALCULATIONS FOR THE YALINA THERMAL FACILITY

A. Wojciechowski, M. Szuta Institute of Atomic Energy

YALINA-Thermal benchmark [1,2] is a part of the IAEA Coordinated Research Projects Analytical and Experimental Analysis of Accelerator Driven Systems and Low Enriched Uranium Fuel Utilization in Accel-erator Driven Sub-Critical Assembly Systems. The 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 the results of different calculations, performed by dif-ferent research institutes, and experimental data.

In this work we present preliminary results of cal-culation using MCNP4 [3] and MCNP5 [4] codes. The geometry is based on the specification of the YALINA-Thermal assembly [2].

Yalina-Thermal assembly uses EK-10 type fuel rods and external neutron sources based on the fusion reactions D-D (2.5MeV) and D-T (14MeV). Calcula-tions [5] were performed for six different arrangements of fuel rods and external neutron sources (Table 1).

Table 1. Experimental arrangements studied.

Number of EK-10 fuel rods

Mass of 235U [kg] Energy of external

neutron source [MeV]

280 2.16 14.0 280 2.16 2.5 245 1.99 14.0 245 1.89 2.5 216 1.67 14.0 216 1.67 2.5

The time dependence of the spatial distribution of

neutron flux and energy in the experimental channels (EC1 – EC7) was calculated (Fig. 1). The effective multiplication factor (keff) (Fig. 2), multiplication source factor (ks) and average prompt removal lifetime were calculated.

1E-8 1E-7 1E-6

1E+0

1E+1

1E+2

1E+3

1E+4

1E+5

Neu

tron

flux

[1/c

m2*

s]time [s]

External neutronenergy 2.5 MeV216 fuel rods

EC1 z = 25 cm

EC1 z = 0 cm

EC1 z = -20 cm

Fig, 1. Total neutron flux (per one external neutron) time dependence in the experimental channel EC1 at three different position z = 0, +25 cm and -20 cm, 216 EK-10 elements and 2.5 MeV external source.

200 220 240 260 280 300

0.86

0.88

0.90

0.92

0.94

0.96

Kef

f

Number of fuel rods Fig. 2.Calculation results of keff as a function of number of

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)


39

PRESENT STATUS OF IV-GENERATION LEAD-COOLED FAST REACTORS DEVELOPMENT

M. Klisi ńska Institute of Atomic Energy

International Committees GIF and INPRO have set a number of technology goals for Generation IV nuclear energy systems. They should provide sustainable energy generation, promote long-term availability of systems, effectively utilize the fuel, minimize the amount of nuclear waste and reduce the long term fission products, be proliferation resistant, excellent in safety and reliabil-ity, have a very low likelihood and degree of reactor core damage, eliminate the need for external emergency actions, have an overall cost advantage over other en-ergy sources and have a level of financial risk compara-ble to other energy sources. The Lead-cooled Fast Reac-tor (LFR) is one of the six IV-Generation nuclear sys-tems selected by GIF and INPRO.

The first in the world reactors using lead-bismuth eutectic – LBE (55 wt% Bi-45wt% Pb) as a primary coolant were Soviet propulsion reactors used in alpha-class submarines (1972-1983).

LFR, as fast reactor, turns 238U into feasible iso-topes of plutonium so it can breed fuel. Fast Breeder Reactors can utilize uranium at least 60 times more efficiently than thermal spectrum reactor.

In contrast to sodium-cooled reactor the lead- and lead-bismuth eutectic-cooled reactors are safer due to the properties of the coolant. Lead and lead-bismuth eutectic do not react vigorously with water or steam and do not burn when exposed to air. This chemical inert-ness enables elimination of intermediate loop in the heat transport circuits with corresponding cost savings. Lead and lead alloys exhibit low neutron absorption and low neutron slowing down power (this is important in fast reactors) and are also effective as neutron reflectors, which enables reduction of fuel enrichment. Heavy metal is an excellent gamma ray shield. Both coolants have relatively low melting temperature – 327°C for lead and 123.5°C for LBE (98°C for sodium), extremely high boiling temperature at atmospheric pressure – 1750°C for lead and 1670°C for LBE – and high heat of vaporization as well low vapour pressure at operating temperature. These properties enable using an ambient pressure primary system and high pressure cooling

circuit. The feasibility of primary coolant pump elimina-tion has been confirmed. Most of LFR designs have no separate steam generators. The working steam is gener-ated by direct contact of feed-water and liquid metal in reactor vessel and then is sent to the turbine. For the steam Rankine cycle subcritical and supercritical op-tions are considered. The presence of light fluid above the core drives natural circulation of the coolant. The simplification of heat transport system allows remote deployment of lead-cooled systems.

The experience with lead-cooled reactors is rather scarce and requires research and development. The main issue is the incompatibility of the coolant with the struc-tural and cladding materials. Cladding material must be also suitable for high-exposure of fast neutrons. Struc-tural material corrosion, coolant activation and chemis-try, filtration of impurities are investigated in several research centers all over the world. The major issue, associated with direct heat transfer from liquid metal to water, is entrainment and carry over of primary coolant vapour and Polonium (210Po is produced by 209Bi activa-tion) into the energy conversion system. Four fuel types are being considered: mixed-nitride (UN-PuN), metallic (U-Pu-Zr), oxide (UO2-PuO2) and carbide (UPuC).

Currently achieved core coolant outlet temperature is limited by material properties to 550–600°C, but in the future it can be extended into the 750–800°C range, which is suitable for hydrogen production. In addition the Pb-alloy cooled reactors are capable of burning actinides and long-life fission products contained in the spent fuel of LWRs.

Sizes of the lead-alloy-cooled reactors designs are broad in scope: from small plants of 6 to 100 MWe – Angstrem (6 MWe), ENHS (50 MWe), LSPR (53 MWe), SSTAR (10÷100 MWe), SVBR-75 (75 MWe), through medium – BREST-300 (300 MWe), to large – BREST-1200 (1200MWe).

References [1] M. Klisińska, Raport IAE-128/A, in Polish (2007)


40

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-velopments in the energy sector in Poland was com-pleted by the end of 2007 [1]. Looking ahead to 2030, the study aimed to identify energy-related technologies, scenarios, a mix of energy sources and infrastructure developments for Poland. One of the key requirements was seen as a re-assessment of the future role of nuclear power in Poland to ensure security of power supply and diversity, and avoid dominance by coal for reduction of CO2 emissions.

The paper [2] provides a short description of the methodology applied as well as main results and find-ings of the foresight study referring to the perspective of 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. 1. Research phases of the study to create Road Maps for nu clear option development.

The process was launched with STEEP and SWOT analysis aimed at isolating the main drivers of Polish future energy system. These analyses were useful to establish the preliminary list of possible variables re-lated to future energy demand and supply as well as economical, political and social fields, which are likely to have an important influence on the future develop-ment of nuclear option.

The Road Maps with detailed time frame for each implementation phase of the individual technology within three scenarios have been developed (Fig. 2). Similar to those R&D Road Maps have been designed with specification of the required actions.

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

[2] J. Szczurek et al., Nuclear Power Component in Fore-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


41

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 4π geometry and practically without limitation on their energy [2], except to the case of the reaction at 30 GeV/c which is selected to follow the energy behav-ior of the investigated correlation only. Simple analytic parameterizations of investigated correlations have been obtained, too. As an example of our results we present here the dependence on IP of the average multiplicity and average rapidity of neutral pions produced in the reaction of πXe at 3.5 GeV/c calculated with the JAM code (Fig. 1).

Fig. 1. Average multiplicity of neutral pions vs. impact para-meter (left) and average rapidity vs. impact parameter (right) calculated using the JAM code [1] for the reac-tion of charged pions with xenon nuclei at four incident momenta: 2.34, 3.5, 9 and 30 GeV/c.

References [1] Y. Nara et al., Phys.Rev. C61, 024901 (2000) [2] L.S. Okhrimenko et al., JINR Rapid Communications.

2(22)-87, 12


42

PARAMETRIZATION OF FLUCTUATION OF ENERGY LOSS IN ELECTROMAGNETIC CASCADES AT INTERMEDIATE ENERGIE S

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:

)./exp()( γα δβAAA tttP −⋅= (1)

Our results show that all parameters attain their as-ymptotic regimes at Eγ ~ 600 MeV. The behavior is demonstrated in the parameter γ distributions vs Eγ for various Ec.o (Fig. 1). The calculations were performed for two values, 0.5 and 0.7, of the threshold A, i.e. the part A at the EC depths at which released is, on the average, 0.5 and 0.7 of the total EC energy loss, corre-spondingly. Analogous distributions have been obtained for β and δ parameters. The conclusion is that near the 600 MeV the description of LEL fluctuation in the form (1) turns out to be universal.

Fig. 1. Distributions on gamma quanta energy Eγ of the pa-rameter γ for two threshold values A at which the part A=0.5 and A=0.7 of EC energy is released on aver-age. The cascades are initiated in liquid xenon by gamma quanta of energy Eγ at the cut-off energy Ec.o. = 0.6, 1.25, 2.0 and 3.0 MeV.

References [1] B. Słowiński, Phys.Part.Nucl. 25, March-April 1994,

173, Radiat.Phys.Chem. 49 327 (1997) [2] C. Grupen, Particle detectors. Cambridge University

Press. (1996) [3] W.R. Nelson et al., The EGS4 Code System. SLAC-265

(1985)


43

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 profile of electromagnetic cascades (EMC) initiated by high energy gamma quanta in uniform amorphous me-dia may be satisfactorily parameterized by a gamma-type function:

),/exp()( t

b

tt cttatf t −⋅⋅=

where the parameters at, bt and ct are to be determined by fitting to experimental data for some materials being of interest (e.g. [1]). Among these parameters mainly ct

depends both on the cut-off energy Ec.o. of cascade par-ticles and material characteristics. Somewhat more ambiguous is the description of radial EMC profiles but from the viewpoint of simplicity one can admit that the relevant distribution is of the form of the weighted sum of two exponents

)/exp()/exp()( rrrrr drcbrarf −⋅+−⋅=

where the parameters ar, br, cr and dr containing infor-mation about the initial and cut-off energies, and on a

medium, should be calculated as the best fit to the rele-vant experimental results [1].

In the work the simulation of EMC developing in the six most frequently used materials: Bi4Ge3O12 (BGO), CdWO4 (CWO), liquid Xe, W, PbWO4 (PWO) and Si has been performed for three values of primary energy Eγ: 500, 1500 and 3000 MeV (i.e., covering the characteristic transition region) and two values of Ec.o.: 0.6 and 1.25 MeV (i.e., as typical for most experi-ments). For each set of parameters (i.e. material, Eγ and Ec.o.) 5000 histories were traced using the EGS code [2] and all parameters determining both longitudinal and radial EMC profiles have been estimated. The depend-ence of the slope parameter ct on the medium character-istics ρZ/A, where ρ is the medium density, Z and A are its electric charge and atomic number (or corresponding average values for compounds) have been determined (Fig.1). Moreover, it has been found, that the above mentioned parameterization functions correspond with 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)


44

ANALYSIS OF PROSPECTS OF WIND ENERGY IN POLAND A. Strupczewski


In view of the large subsidies to wind power and plans of its fast development there is a new discussion on whether it is necessary do develop nuclear power, if the renewable energy sources can be made available. The example of Denmark is quoted as the case of a country which is very successful in developing wind power. On the other hand, Both European Parliament and governments of such countries as France and UK 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. 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 practice the wind power is much less than the maximum rated value, so e.g. in Germany the average annual load factors for wind turbines range from 16 to 20%.

Fast changes of wind power can not be compensa-ted by coal fired power plants. Gas can partly help, but the real answer lies in hydropower, which can be easily regulated. Denmark is fortunately situated close to the large hydropower system of Scandinavia, which pro-duces 178 TWh/a and can accommodate both sudden increases and decreases of wind power. But Denmark has to pay for it – it must send most of its energy abroad at dumping price, and so loses annually one billion Danish crowns [2].

Capital costs for wind power are very high. A comparison of an NPP with the load factor of 0.88, which is less than the actual average value in the world, and wind power plants with load factors of 0.,34 on land and 0.45 offshore [3] – which is very high for wind turbines - shows that the capital costs per unit of energy generated over the lifetime are much higher for wind than for nuclear power plants [1].

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. 3. Wind velocity in Poland at the seaside (blue line) and in south regions (dashed red line) [1].

Moreover, the power of the hydropower is small in Poland which makes problems of compensation of wind changes very difficult. Thus although wind power is renewable, and so should be used in Poland, related costs will be high.

References [1] A. Strupczewski, Biuletyn PSE, 4-5 4 (2007) [2] H. Sharman, Civil Eng. 158 66 (2005) [3] J. Eliasz, A. Biwan , Energetyka 2006, Wrocław Uni-

versity of Technology, 8 – 10 November (2006)


45

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 from coal fired power plants. In the European Union the dominating electricity source is nuclear power, which in 2004 provi8ded about 32% of overall needs. Coal provided 29.7% of electricity needed in the EU, and gas 18% [1].

Nuclear power offers Poland advantages in three respects:

- Security of supply, important in view of the limita-tions of possibilities of use of coal.

- Economical profits, as nuclear power is presently the lowest cost stable energy Skurce.

- Health and environmental protection, as nuclear power means clean air, water and soil around the NPPs.

CO2 emission permits introduced by the European Commission which add to the price of coal about 22 euro/ton CO2, and even more the emission permits which limit Polish emissions much below actual use, are very strong incentives to stop building coal fired power plants. Nuclear power is economically competitive even without consideration of emission permits [1]. Nuclear industry has made great progress on the road of reduc-tion of capital costs and improvement of operational parameters and is presently the lowest cost energy sour-ce (Fig. 1).

The operational resources of organic energy source in Poland will be exhausted within some 40 years after

which it will be necessary to build much deeper coal mines and produce coal at much higher costs.

Polish economy develops and is expected to conti-nue this trend so that in 2025 the electricity needed in Poland will be 220 TWh. An analysis of existing and potential energy sources has shown, that without nuclear power the energy needs cannot be satisfied.

Coal production is slowly decreasing year after year. Gas contribution should not be assumed, because in near future the availability o gas will go down, and its goes up. Thus, if we assume that in 2025 coal and gas will keep their present production quotas (143 TWh/a), it will be an optimistic view.

Renewable energy sources in Poland are quite limi-ted and much more expensive than coal or nuclear po-wer. The potential of hydroenergy is presently about 4 TWh/a, and till 2025 further 3 TWH can be devel-oped, biomass can provide up to 6 TWh, biogas (from all resources) up to 14 TWH and wind 8 TWh.

Together this yields 174 TWh. We are short by 46 TWh – and this is the equivalent of 2 NPPs with 2 units of 1600 MWe power each.

Besides being necessary and cheap, nuclear power is also clean The technical studies in the EU [2] and in Poland [1] are in full agreement: the question for Poland is not whether to build NPPs or not, but rather how soon it is technically possible.

0,0

50,0

100,0

150,0

200,0

NPP Gas Coal Lignite

unit

cost

s [P

LN/M

Wh]

Capital

Depreciation

Maintenance

Sorbents

Ash storage

Liquid waste

Water

Emissions

Taxes

Fuel

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


46

ANNUAL REPORT 2007 Condensed Matter Physics

49

REGIONAL LABORATORY OF NEUTRONOGRAPHY J. J. Milczarek, J. Jankowska-Kisielińska, A. Czachor


The Regional Laboratory of Neutronography (RLN) provides experimental facilities and research experience in the field of thermal neutron scattering studies of condensed matter and materials engineering. The laboratory operates six horizontal channels of the MARIA reactor and six instruments designed for elastic and inelastic neutron scattering (Fig. 1). A beam time allocation at our facility can be applied for by submit-ting proposals directly to the responsible researchers mentioned below or to Prof. A. Czachor. Proposals are evaluated by the Project Selection Board of the RLN which consists of the representatives of institutes and universities interested in doing research using neutron scattering at the RLN. The Board's Chairman is Prof. L. Dobrzyński of the Sołtan Institute for Nuclear Stud-ies, Świerk.

M

A

C

C

S

M.

S

A

CS

A

C

M.

A

S

C

M.

M.

SA

C

H3

H4H5

H6

H7

H8

5

6

7

21

Fig. 1. Floor plan of the neutron spectrometers of RLN in the

Maria reactor hall.

Available instruments at horizontal channels (H 3-7) and responsible researchers. 1 H3-a small angle neutron diffractometer designed for

studies of inhomogeneities like precipitations and micropores in materials (λ = 0.237 nm, Qmin≈ 0.1 nm-1). Dr J. J. Milczarek tel. +48 22 7180233

e-mail: [email protected] 2 H3-b double axis diffractometer, used to study crys-

talline or magnetic structures. Zn, PG, Cu(200) and Si(311) monochromators are available. The range of scattering angles: 0º - 90º. The energy analysis of the scattered neutrons is also possible.

Dr J. J. Milczarek tel. +48 22 7180233 e-mail: [email protected] 3 H4 – small-angle double-crystal neutron diffractome-

ter. The instrument operates with monoenergetic neu-

trons (λ = 0.15 nm) monochromatized and analyzed with the (111) Bragg reflection from Si single crys-tals. The full-width at half maximum of the instru-mental distribution is in the region of 30"- 40". The angular distribution of transmitted neutrons may be measured in steps of 0.125". The instrument is de-signed for studies of the average size of magnetic domains, large precipitations or other micro-objects that cause neutron scattering.

Dr J. J. Milczarek tel. +48 22 7180233 e-mail: [email protected] 4 H5 – enhanced resolution diffractometer equipped

with Cu (200) double-crystal monochromator; angular resolution ~4’; neutron wavelength range: 0.06 – 0.1 nm; scattering angle range: 0º - 110°. It may be 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.

Dr J. J. Milczarek tel. +48 22 7180233 e-mail: [email protected] 5 H6 - triple-axis spectrometer. The instrument is de-

signed for studies of the crystal and magnetic lattice dynamics by inelastic neutron scattering. The instru-

ment is equipped with PG (FWHM = 0.4o) mono-

chromator, analyzer and filter set; neutron flux den-

sity at the sample position is 5.1·105cm-2 s-1 for

λ = 0.235 nm. The range of scattering angles: 10º - 110º. Dr J. Jankowska-Kisielińska. tel. +48 22 7180137 e-mail: [email protected]

6 H7 - triple-axis spectrometer, designed for the inelas-tic neutron scattering studies. PG monochromator, analyzer and filter set is installed. Zn monochromator (FWHM = 15') and analyzer set is also available with neutron flux density at the sample position 5.5·105 cm-2 s-1 for λ = 0.152 nm. The range of scat-tering angles: 10º - 110º.

Dr J. Jankowska-Kisielińska. tel. +48 22 7180137 e-mail: [email protected]

Each instrument is computer controlled. The labo-ratory uses an unified computer code for all instruments. The program offers the window system with text and graphics modes, zooming option for data extraction and visualization of measurement results. Available sample environment includes helium microcooler (8 K – 300 K), liquid nitrogen cryostats, vacuum furnaces and magnets. The sample environment parameters can be registered in real time during measurements. The neu-tron and gamma radiography facility installed at the H8 horizontal channel is described in the next section.

Condensed Matter Physics ANNUAL REPORT 2007

50

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, such as Fe, Cu and Al, combined with a strong scatter-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-roded parts. The strong beam of gamma radiation, emit-ted from nuclear reactor, also can be used to provide an extra information on the interior of the object investi-gated. Having passed the investigated object, the neu-tron or gamma radiation reaches the fluorescent screen (converter), where it is converted into visible light (Fig. 1). The two-dimensional projection of the object on the screen is registered with the CCD camera and processed using computer methods.

OBJECT

CONVERTER

MIRROR

LIGHT

ZOOM LENSES

CCD CAMERA

ACQUISITIONSYSTEM

NEUTRONS

Fig. 1. The main parts of the neutron radiography station.

The neutron and gamma radiography (NGR) sta-tion at Świerk is situated at the horizontal beam H8 of the MARIA reactor (Fig. 2). The station has started its operation in July 2001. The following investigations have been performed in 2007: - Temperature and gravitation dependence of water

migration in beds of granular materials. - Nondestructive testing of technical objects. - Observations of drying of wet kaolin samples.

Due to the ample space by the channel H8 of the reactor MARIA and its relatively large neutron flux, this NGR facility has many advantages, especially for diag-nostics of industrial objects. Remote-control support devices and modern analogue and digital registration equipment will allow us to scan and record the internal structure of large objects like engines, refrigerators, as 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-

tion beam and converter screen. The sample support can hold objects with mass to 100 kg.

1 m

H7

H8

object

neutronbeam

colli

mat

ors

beamtrap

water

asphalt

paraffin orneutronstop

opticalsystem

computersystem

Fig. 2. General layout of the neutron and gamma radiography station at the research reactor MARIA.

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 at the sample position for L/D=150. The spatial resolu-tion is of the order of 0.1 mm. The high quality images are produced with the exposition time of 1.6 s, but satis-factory quality of the full resolution radiograms is obtained for the exposition time of 0.6 s.

Good uniformity of the white field was confirmed and the linear resolution of 0.1 mm for the optical mag-nification used in most experiments was established. The result of the resolution test is presented in Fig. 3 containing the radiogram (Fig. 3a) of three 2 mm thick slabs made of cadmium, lead and Plexiglas with holes of 2 mm diameter. The edges of the holes are separated by gaps with widths decreasing from 1 to 0.1 mm up-wards. The optical density plot (Fig. 3b) reveals distinct cusp on the left corresponding to the smallest separation gap (0.1 mm).


51

a

20 30 40 50

distance (mm)

0

0.2

0.4

0.6

0.8

1

1.2

Opt

ical

den

sity

(ar

bitr

ary

uni

ts)

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 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.

Fig. 4. The radiogram of flat double container filled with ordinary water (left part) and heavy water (right side) of 1.3 mm thickness.

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-tion through the damaged paint cover was very rapid leaving the dry region (visible in the radiograms as the blue tilted strip) in the middle of the sample.

The merits of NR are inaccessible within standard X-ray or optical methods, supporting the expectations of interest in NR from many researchers of industrial, agriculture, medical and other roots.

(a) t = 5 s

(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. The time is counted from the switching the voltage sup-ply on.


52

MATERIAL RESEARCH LABORATORY OF THE IEA W. Szteke


The Material Research Laboratory (MRL) of the Institute of Atomic Energy is engaged in research cover-ing all aspects of materials engineering and in techno-logical processes developed in the powder metallurgy, welding, brazing and soldering domains. The investiga-tions are carried out on both structural materials and their welded joints, including the examinations of irra-diated materials. The Laboratory is equipped with mod-ern devices for the scientific and applied studies of materials. All work in MRL is performed according to the Quality Assurance Program.

The MRL incorporates the Hot Laboratory which was put into operation in February 1993 after the au-thorization by the National Inspectorate for Radiation and Nuclear Safety. The facility was designed to pro-vide maximum flexibility for a wide research program involving metallurgical, physical, and chemical testing of irradiated structural materials of nuclear reactors. The main part of the laboratory is a set of 12 hot cells with lead shielding suitable for handling of radioactive mate-rials up to 4 TBq related to 60Co. Every cell is equipped with up-to-date sophisticated devices for examination of radioactive materials. The main equipment includes:

- Instron 8500 Dynamic Testing System with two 100 kN frames for testing of tensile and compres-sive strengths, low cycle fatigue resistance, fracture toughness, bend characteristics and crack growth resistance at -150˚C to 1000˚C temperature range.

- Instrumented Wolpert Pendulum Impact Testing Machine PW 30/15 for dynamic tests of Charpy-V type specimens carried out at -150˚C to 800˚C tem-perature range, for determination of significant force and deflection values, partial energy values, characteristic fracture mechanical values.

- DIA-TESTOR 7521 Wolpert Hardness Testing Machine for tests using Brinell, Vickers and Rock-well procedures.

- DRD-4 X-ray Diffractometer for structure analysis,

- ROBOFIL 200 Spark Erosion Machine for speci-mens preparation.

The devices are fully automated, remotely op-erated and instrumented, equipped with computer con-trol systems for machine control, data acquisition and analysis of results.

The remaining equipment of the hot cells complex provides an opportunity to perform:

- cutting out samples from the irradiated reactor components,

- sample preparation for metallographic and X-ray examinations,

- thinning of metal samples for transmission electron microscopy,

- optical microscopy and microhardness measure-ments,

- swelling control of materials and density determination,

- thermal treatment and annealing, - stereo macroscopic examination and stereo photog-

raphy, - chemical analysis.

At the end of 1998 the laboratory for non-destructive testing of materials was put into operation in the MRL. The applied test methods include: - visual inspection, - liquid penetration inspection, - ultrasonic examination, - radiographic inspection, including X-ray and iso-

tope radiography, - structure investigation using replicas method.

Since 1999 the MRL has been the exclusive repre-sentative of the SAQ Kontroll AB Sweden in Poland for using and promoting in Poland the special diagnostic programme SACC 4.0 (Safety Assessment of Compo-nents with Cracks).

The experience of the Material Research Labora-tory in radioactive materials analysis was employed in Materials Testing Centre formed within the consortium of the IEA and the Radioactive Waste Management Plant for quick identification and categorization of ra-dioactive or nuclear items of unidentified or unknown origin. The Materials Test Centre is a part of Polish system for response to illicit trafficking and inadvertent movement of radioactive materials. The main equip-ment of the MTC consists of:

- ISOCS Shield System for in situ gamma spectros-copy with a germanium detector.

- InSpector 1000 – portable NaI gamma spectrometer with neutron probe.

- Radiagem 2000 – portable dose rate meter with two intelligent probes SABG 15 and SAB 100 for alfa, beta and gamma radiation.

MRL IAE holds the Accreditation Certificate of Testing Laboratory No AB 025 which confirms fulfill-ment of the ISO/IEC 17025:2001 criteria and the Tech-nical Requirements of Technical Inspection DT-L/95.


53

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 experimentally for a majority of isotopes in last decades [1], one can extract systematic information on some nuclear properties. The intriguing „scatter” of the ex-perimental values of b, showing no systematic depend-ence on the mass number A or charge number Z needs interpretation. In this work, on extending the use of known formulas of the theory of neutron scattering on nucleus represented by a rectangular radial symmetry potential well (or barrier), we have determined the depths V0 of the potential well and for many isotopes the position of the bound state energy level EB in the well.

Fig. 1. Graphical representation of three possible types of rectangular radial-symmetry potential wells (barriers) - Colors show three domains of solutions of Eq. (2), depending on the ratio of neutron scattering length b to the “classic” nucleon radius R). Yellow - shallow well, V0 < 0, b < 0; violet - potential barrier, V0 > 0, 0 < b < R; green - deep well, V0 < 0, b > R,

We have chosen the simplest model of the radial rectangular potential well of the depth V0, and the radius

3/1AorAR = (1)

with r0 = 1.3 fm.

On assuming the „attractive” rectangular potential

well of the radius ARR = and the depth 0<ZAV , one

arrives under the usual boundary conditions at the equa-tion relating the potential depth and scattering length

x

tgx

AR

b =−1 (2)

where

ARZAmVx 21 −−= h (3)

The construction of Eq. (2) allows three possibili-ties for the left hand side, corresponding to three essen-tially different potential wells (Fig.1).

It has appeared, that for the deep potentials the po-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].

-80

-75

-70

-65

-60

-55

-50

-45

-40

-35

-30

-25

-20

0 15 30 45 60 75 90 105 120 135 150 165 180 195 210 225 240 255

A

V0

Fig. 2. Potential well depths for deep wells. They were as-signed to 4 domains of possible solutions of Eq. (2): The

0≠S isotopes are included as dark green points.

References [1] Neutron Data Booklet, Ed. Dianoux A. J., Lander G.,

ILL – Neutrons for Science, (2001) [2] T. Mayer-Kuckuk, Kernphysik, Teubner B. G.,

Stuttgard, (1979) [3] A. Czachor, P. Pęczkowski, IAE Report B-59 (2007)


54

GROWTH DEFECTS AND LATTICE DEFORMATION IN Ca0.5Sr0.5NdAlO 4 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 (where A = Ca, Sr, Ba, B = La, Nd, Pr and C = Al, Ga) 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 thermal properties and a good lattice matching. Crystals of high structural quality are required for such applica-tions hence the characterization of crystal lattice defects is of a great importance. The crystals of solid solution in AxA’ 1-xBCO4 or ABCxC’1-xO4 systems provide a possi-bility of obtaining the adjustable lattice parameter by appropriate selection of the A/A’ or C/C’ ratio [1-6].

The Ca0.5Sr0.5NdAlO4 single crystal grown by the Czochralski method in the [100] direction was chosen for studies. The investigations were performed using 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.

The synchrotron back reflection topographs ex-posed through the mesh revealed the local lattice misori-entation associated with a lattice parameter change. The local lattice misorientation manifests itself in bending of shadows of the wires (Fig. 1).

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

which may indicate the deformation of the lattice (marked by D in Fig. 2.

Fig. 2. Synchrotron radiation white beam transmission section topograph of Ca0.5Sr0.5NdAlO4 single crystal, -36-7 re-flection, λ = 0.047 nm.

The synchrotron back reflection monochromatic topographs revealed long-range lattice deformation of the sample (Fig. 3).

Apart from striations the white beam back reflec-tion topographs revealed a significant concentration of individual defects in form of precipitates and disloca-tions. The nature of the observed defects is under inves-tigation.

Fig. 3. Synchrotron radiation monochromatic beam back

reflection topograph taken at low-angle rocking curve flank, 400 reflection, λ = 0.111 nm.

References [1] M. Berkowski et al., Appl. Phys. Lett. 57 632 (1990) [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.


55

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 A IIIBV single crystals are stimulated by the demand for substrates with well-defined lattice parameters and en-ergy gap. It is, however, a difficult task due to segrega-tion phenomena occurring in multicomponent liquid solutions of AIIIBV compounds [1]. Therefore, only thin layers are easily grown using epitaxial techniques on the relevant binary substrates. In the reported case the GaAs1-xPx and GaAs1–xPx:Te (x ≤ 0.2) ingots were grown at a significantly reduced growth velocity (~1 mm/h) in order to control supersaturation in the melt. 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 segregation fringes and other lattice defec. It should be noted that transmission section topographs provided an image of segregation fringes along the intersection of the narrow incident beam with the sample.

Fig. 1. Back reflection projection topograph of GaAs1–x Px:Te sample.

It was found that that the topographs of the doped sample of GaAs1–xPx:Te (Fig. 1) exhibits a complicated contrast connected with instabilities of the growth front. In some regions a more distinct lattice deformation as well as some extended contrasts are observed. They may be connected with inclusions of not perfectly crys-tallised material. On the other hand, the topographs of undoped crystal (Fig. 2) exhibited a much better perfec-tion, with much more regular growth bands. However, some growth instabilities are still visible in the left part of the picture.

Fig. 2. Back reflection projection topograph of GaAs1–xPx sample.

The transmission section topograph of the undoped 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 [1] H. J. Sell, J. Cryst. Growth 107, 625 (1991) [2] G. Kowalski et al., phys. stat. sol. (a) 204, 2578 (2007)


56

CRYSTALLOGRAPHIC DEFECTS AND FACETING IN Er-DOPED Yb 3AL 5O12 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 Yb3Al 5O12: 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 Yb3Al 5O12 (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-bility of growing Yb3Al 5O12 crystal of good structural quality with high concentration of erbium dopant. The most important observed defects were segregation fringes and growth facets. The monochromatic beam topographs confirmed slight changes of lattice parame-ter induced by the segregation of the erbium and low level of strains in the crystals (Fig. 1, 2).

Fig. 1. Monochromatic beam back reflection topograph in symmetrical 444 reflection of Yb3Al5O12 crystal with 1.5% of erbium in 0.111 nm radiation exhibiting segre-gation fringes and some rosettes corresponding to the dislocation outcrops.

a b

Fig. 2. White beam projection back reflection topographs of Er doped Yb3Al5O12 crystals revealing segregation fringes and sets of facets: a – with 10% erbium, b – 1.5% erbium.

The observed facets were identified as correspond-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-sion section topographs, which show the location of growth bands in the intersection of the sample with the incident synchrotron beam, and enabled us to determine the curvature of the growth surface (Fig. 3).

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)


57

TOPOGRAPHIC STUDIES OF GROWTH DEFECTS IN YVO 4 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


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.

A number of samples cut out from Czochralski 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 the crystal close to its boundary the glide bands were observed (Fig. 1).

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-tion forms a local subgrain boundaries. A complicated structure of subgrain boundaries may be seen in Fig. 2. The topographs did not reveal any segregation fringes proving high homogeneity of chemical composition.

The misorientation of the lattice connected with these boundaries was studied in some synchrotron monochromatic beam experiments in multicrystal ar-rangement (Fig. 3). The experiment allowed us to find the misorientations less than few minutes of arc.

Fig. 2. Complex subgrain boundary structure revealed by white beam topograph in the sample cut out from an-other part of the crystal.

a

b

c

Fig. 3 a - c. Monochromatic plane wave topographs: (400) reflection,λ = 0.115nm, direction of the beam projec-tion along the normal to (001) planes. The pictures were taken for three angular positions passing the ma-ximum of the rocking curve.

References [1] S. Wu et al., J. Cryst. Growth 249 176A (2003) [2] H. Zhang et al., J. Cryst. Growth 283 438 (2005) [3] Y. Yu etal., Materials Letters 60 1014 (2006), J. Cryst.

Growth 249 176 (2003)


58

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


The interest in multicrystalline silicon comes from the possibility of replacing the crystalline silicon by cheaper material in some applications like photovoltaic technology. The main concern is the homogeneity of 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 information on the grain sizes and their angular distribu-tion (Fig. 1). In many cases the method revealed many details of the defect structure of particular silicon grains (Fig. 2).

a b

Fig. 1. Synchrotron white beam projection back reflection patterns taken at glancing angle of 5º, a – reference sample and b 100 h NTD annealed sample.

The observed defects included some subgrain structure connected with glide bands as well as some distinct black contrasts which may be attributed to some inclusions. It was not possible to find a direct connec-

tion between the defect structure and the irradia-tion/annealing processes. We hope that further studies help to identify some observed changes in the subgrain structure as produced by this treatment.

a b

Fig. 2. White beam topographs (enlarged images) of selected grains revealing subgrain structure and glide bands.

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).

Fig. 3. The interference fringes in Bragg-case section topog-raph caused by sample curvature proving the coher-ence of defect clusters in annealed NTD sample.

The interesting phenomenon was the decrease of the diffraction peak width for higher irradiation dose and higher annealing temperature.


59

ANISOTROPY OF THE NEUTRON SCATTERING ON THE Mn 0.71Ni0.29 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-tial anisotropy of the critical neutron scattering in the paramagnetic phase and the anisotropy of spin-waves in the antiferromagnetic phase of the Mn0.71Ni0.29 alloy.

The earlier study of the critical scattering in the FCC Mn0.62Ni0.38 demonstrated the pronounced uniaxial anisotropy both in the static and dynamical part of the generalized susceptibility [1]. The anisotropy axis is parallel to the scattering-vector reduced to the paramag-netic Brillouin zone. The spin-wave velocities for this alloy were 21 and 15 meV nm for the spin wave vector parallel and perpendicular to the anisotropy axis [2]. It should be stressed that any significant anisotropy of the SW scattering was found neither in FCC Mn-Fe alloys nor in Mn-Ni alloys with the tetragonal structure (Mn0.843Ni0.137, inter-metallic compound MnNi). It was also not mentioned for FCC Mn0.73Ni0.27 [3]. The ques-tion, what is the reason of the strong anisotropy ob-served in Mn0.62Ni0.38 alloy, is still open. The present extension of our study on the Mn-Ni alloys aims to find the concentration dependence of the anisotropy.

Our main result for the paramagnetic phase of the Mn0.71Ni0.29 alloy is that the correlation length is bigger for the direction parallel to the anisotropy axis than for the perpendicular one (Fig. 1). The ratio obtained at 35K and 45K above TN is κ⊥/κ|| = 1.5±0.2, where κ⊥ and κ|| are the reciprocal correlation lengths for perpendicu-lar and parallel directions. The same ratio obtained earlier for the Mn0.62Ni0.38 was 2±0.2 for temperature range 5-100K above TN.

-0.3 -0.2 -0.1 0 0.1 0.2 0.3X

0

40

80

120

160

200

Inte

nsi

ty

(0,1+X,0)

(X,1,0)

Fig. 1. The intensity distribution of the paramagnetic neutron scattered with energy 5.5 meV measured at 453K for [100] direction (open symbols) and [010] direction (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.

The SW neutron-scattering was measured for the both parallel and perpendicular directions for energy up to 18 meV (Fig. 2). The SW velocity is higher for the direction parallel to the anisotropy axis than for the perpendicular direction, but the difference is close to the accuracy limits: v|| = 19±1 meV nm and v⊥ = 16±1 meV nm obtained from data for 18 meV for 15K. The SW damping was found similar for the two directions.

-0.2 -0.1 0 0.1 0.2X

0

100

200

300

400Inte

nsi

ty

0

100

200

300

400(X,1,0)

(0,1+X,0)

Fig. 2. The intensity distribution of the neutron scattered on spin waves with energy 18 meV measured at 15K for [100]-upper part and [010] direction in the vicinity of the (010) reciprocal lattice point. The dashed lines rep-resent the shape of the scattering cross-section and the solid lines –the folding of the cross-section with the resolution function.

In conclusion, we found the anisotropy of the cor-relation range in the paramagnetic phase and of the observed spin wave velocity in the AF phase in the Mn0.71Ni0.29 alloy. The effect it is less pronounced than similar anisotropy found in the Mn0.62Ni0.38 alloy. Our result indicates that magnetic interactions in Mn-Ni alloys are less extended for higher Ni concentration.

References [1] J.J. Milczarek, et.al., J. de Physique 49 C8 183 (1988) [2] K. Mikke, J. Jankowska-Kisielińska, B. Hennion, Ap-

plied Physics A 74 Suppl., S616-S618 (2002) [3] B. Hennion, M. T. Hutchings, R. P. Lowde, M. W.

Stringfellow, D. Tocchetti, Proc. 2-nd Gatlinburg Conf. on Neutron Scattering, (R. M. Moon, editor) 825 (1976)


60

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 imbibition of beds of coarse granular media such as sand or gravel depends on the direction of the water front migration against gravity [1,2]. The aim of this work was to study the effect of gravity on the kinetics of water migration in unsaturated (dry) simple granular systems composed of chemically uniform grains of selected size.

The present studies [3,4] were performed on quartz sand and corundum beds of different grain size (Table 1). The beds were in the form of ~130 mm long and ~7 mm diameter cylinders and were placed verti-cally at stabilized temperature. It was possible to supply lower or upper end of the sample with water inducing the migration opposite or according to the gravity, re-spectively.

1 10 100t [s]

10

100

d [m

m]

fine quartz50 °C

1 10 100t [s]

10

100

d [m

m]

corundum50°C

Fig. 1. Dependence of the position of water front on time in

fine quartz and corundum beds at 50ºC. The vertical arrows, ↓ and ↑, indicate the direction of the wetting front motion, according and opposite to the gravity, re-spectively.

The experiments were carried out with the dynami-cal neutron radiography with spatial resolution of 0.2 mm, with frames recorded every 2 s. The effect of the gravity on the water front motion was discernible even for beds composed of fine grains (Fig. 1).

The experimental results were analysed in terms of the Washburn-Bosanquet (W-B) theory of water migra-tion in porous medium. Assuming the correctness of the W-B description for the initial stages of the imbibition the effective capillary radius was estimated from the imbibition rate parameter a (Table 1). However, our analysis reveal that the theory is not valid for overall time behaviour of wetting front motion (Fig. 2) [3, 4]. Our results suggest that the main reason for this serious discrepancy is that the theoretical approach underesti-mates the energy dissipation in the migration of liquid in the porous medium neglecting the roughness of pore surface boundary.

Table 1. Effective porosity, imbibition rate parameter and effective capillary radius of the bed.

material grain size

[mm]

imbibition rate parameter

at 30°C [mm s-1/2]

effective capillary radius ar

[µm]

fine quartz 0.09 – 0.16 8 1.45 coarse quartz 1.0 – 1.2 5.4 0.65 corundum ~0.05 4.8 0.52

1 10 100t [s]

10

100

d [m

m]

fine quartz30°C

theoryr = 1.5 µm

theoryr = 0.1 mm

↓↑

Fig. 2. Comparison of the W-B theory predictions and experi-mental results for the time dependence of the imbibition front position in fine quartz bed.

References [1] J.J. Milczarek et al., IAE Report B-31 (2004) [2] J.J. Milczarek et al., IAE Report B-45 (2006) [3] J.J. Milczarek et al., IAE Report B-36 (2007) [4] J.J. Milczarek et al., Acta Phys. Pol. A 113 1245 (2008)


61

NEUTRON RADIOGRAPHY STUDIES OF DRYING KAOLIN SAMPLE S J.J. Milczarek1, I. Fijał-Kirejczyk 1, J. śołądek1, J. Banaszak2, Z. Jurkowski 1, 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 solid bodies are of importance for technology and theo-retical model construction [1-3]. The aim of our work [4] was to apply the dynamic neutron radiography in observations of drying of kaolin cylinders.

The present studies [3] were performed on the 30% wet kaolin cylinder (25.4 mm high, 27.3 mm diameter). The sample was observed for 72 hours during convec-tive drying at temperature of ~18°C.

t = 0 t = 20 h t = 72 h

Fig. 1. Neutron radiography images of drying kaolin cylinder. The time elapsed from the beginning of the process is given below of each image.

The experiments were carried out with the dynami-cal neutron radiography with spatial resolution of 0.2 mm. The brightness of the sample images registered during the process increased with time (Fig. 1).

The experimental results were analyzed in terms of the usually assumed exponential dependence of the neutron beam intensity I on the composition and thick-ness L of the sample:

L

o eII Σ−=

where the macroscopic neutron cross section Σ de-pends substantially on the chemical composition of the material [5].

In order to discuss the changes in the water content of the sample the effective macroscopic neutron cross section effΣ was calculated from the local optical den-

sity D in the specific point of the sample image

∑−−ℜ

=eff

oxxR

D

))((2 22

where R denotes the cylinder radius, ox is position of

the cylinder axis on the horizontal Ox line, and ℜ is the operation of extracting of the real component.

The significant differences in the spatial depend-ence of the effΣ calculated for different times of drying

were found (Fig. 2).

36 40 44 48 52 56 60 64position [mm]

0

0.05

0.1

0.15

Σ eff

0 h3 h20 h72 h

Fig. 2. Neutron macroscopic cros- section along the central horizontal line of drying kaolin cylinder.

Our results reveal the decreasing water content in-side the drying kaolin cylinder. It seems that initially the water is distributed less uniformly than in the later stages of the drying process. However, the strong scat-tering component makes the determination of the water content distribution difficult. The estimation of the spatial distribution of water should be based on simula-tions taking into account both neutron absorption and scattering in the sample.

References [1] Porous media: Theory and Experiments, R. de Boer

(Ed.) Kluwer, Dordrecht (1999) [2] S.J. Kowalski in Porous Media, W. Ehlers, J. Blum

(Eds), Springer, Berlin (2002) [3] G. Musielak, J. Banaszak, Transp. Porous Med. 66 121

(2007) [4] J.J. Milczarek, et al. IAE Report B-58 (2007) [5] Practical Neutron Radiography, J.C. Domanus (Ed.),

Kluwer, Dordrecht (1992)


62

NEUTRON SCATTERING STUDIES OF WO3:ZrO 2 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 WO3 : ZrO2 composites produced by sol-gel tech-nique [1, 2] and annealed at 500, 650 and 800°C was studied by wide and small angle neutron diffraction [3].

The atomic ordering of the composites was studied in the wide range (10 – 80 nm-1) of the scattering vector Q . It was found that the diffractograms for samples

annealed at 500°C do not reveal any Bragg peaks but only a broad halo centered near Q of 40 nm-1 (Fig. 1a). For samples annealed at 650ºC four distinct maxima were observed for each composition. The diffracto-grams of 800ºC annealed samples consist of many Bragg peaks (Fig. 1b) characteristic for fully fledged crystalline structure.

a 0 20 40 60 80

Q [nm-1]

0

20

40

60

80

100

Inte

nsi

ty [

coun

ts]

wzr_031:1 500°C 5h

b 0 20 40 60 80

Q [nm-1]

400

800

1200

Inte

nsity

[co

unts

]

wzr_05 1:1 800°C 5h

Fig. 1. Neutron diffraction pattern for 1:1 WO3 : ZrO2 nano-composite after two different thermal treatments.

The nano-scale structure of the composites was de-termined by the small angle neutron scattering in 0.1 nm-1 << Q 1 nm-1 region. The analysis of the SANS

data was performed with the GIFT program of the PCG package [4] in order to obtain the distance correlation function P(r) and the structure factor S(Q).

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).

The elongation of the inhomogeneities was found also for 1:1 and 3:2 composites. However, the space correla-tion of their positions is much weaker than that for 1:2 composites even after 500°C annealing.

a 0 10 20 30 40 50

r [nm]

0

4

8

12

P(r

)

1:2500°C 5h

b 0 20 40 60

r [nm]

0

10

20

30P

(r)

1:2800°C 2h

Fig. 2. The plots of distance correlation function P(r) for 3: 2 WO3 : ZrO2 nanocomposite after the 500°C and 800°C annealing.

Our results [3] confirm that the WO3 : ZrO2 com-posites easily crystallize and the rate of process in-creases with the temperature. We found that in the com-posites annealed at 500°C the inhomogeneities of aver-age diameter of 50 nm and highly warped boundary surface exist. For higher annealing temperatures the cylinder-like particles are formed.

References [1] M.S. Dadachov et al., Appl. Radiation and Isotope 57

641 (2002) [2] A. Deptuła et al., Polish Patent No. 172618 (1997) [3] J.J. Milczarek et al., IAE Report B-38 (2007) [4] J. Brunner-Popela, O. Glatter, J. Appl. Cryst. 30 431

(1997)


63

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


The heavy rare earth (R) - transition metal (M) ferri-magnets RM2, including substituted ferrimagnets, have been widely studied for both their fundamental interest and practical applications [1,2]. The ferrimagnetism of the RM2 compounds results from the coexistence of 4f(5d) and 3d magnetism [3]. The present work aim was the effect of the substitution of Fe with Ni in the Dy(Fe0.7Co0.3)2 compound (Fe/Ni substitution introduces 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. 1. 57Fe Mössbauer effect spectra of the Dy(Fe0.7-xNix Co0.3)2 intermetallics (4.2K).

The spectra are composed of a number of subspec-tra and this complexity arises from the different nearest neighborhoods of the observed Fe-atoms resulting from Fe/Ni substitution. Each Fe, Ni, Co nearest neighbor surrounding introduces its own subspectrum and thus its own set of hyperfine interaction parameters. The prob-lems in determining the number of nearest neighbour 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-

tice, is analogous for that for other intermetallic series [5].

The average values of the hyperfine interaction pa-rameters at 4.2K, estimated from the fitting procedure i.e., the isomer shift IS (with respect to pure iron metal, at 300K), the magnetic hyperfine field µ0Hhf and the quadrupole interaction parameter QS have been deter-mined for seven equidistant x values (Fig. 2).

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 (Fig. 2.3)

References [1] A.M. Tishin, Y.I. Spichkin, The Magnetocaloric

Effect and its Applications, Institute of Physics, 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] A. Jabłońska et al., J. Alloys Compd. (in press) [5] P. Stoch et al., J. Alloys Compd. 375 24 (2004)


64

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


The heavy rare earth (R) - transition metal (M) ferrimagnets RM2, including substituted ferrimagnets, have been widely studied for both their fundamental interest and their practical applications [1,2]. The ferri-magnetism of the RM2 compounds results from the 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 out for randomly positioned Fe, Co and Ni atoms on the sites of the transition metal sublattice.

The average stoichiometrically weighted density of 3d states (DOS), per transition metal, and the densities of 3d states, for Fe, Co and Ni, were calculated. An example of the results is presented for the Dy(Fe0.7Co0.3)2 and Dy(Fe0.2Ni0.5Co0.3)2 compounds (Fig. 1).

Fig. 1. Weighted (M) and individual (Fe, Co and Ni) densities of 3d electrons states (DOS) as functions of energy E.

The magnetic moments per Fe, Co and Ni atom and the stoichiometrically weighted moments per transition metal atom calculated for the Dy(Fe0.7-xNixCo0.3)2 series decrease with increasing number of 3d electrons per atom (Fig. 2).

Fig. 2. The calculated magnetic moment mM of transition metals vs. average number n of 3d electrons for the Dy(Fe0.7-xNixCo0.3)2 series (1 - M=Fe, 2 - M=Co, 3 - M=Ni, 4 - weighted magnetic moment per transition metal atom).

The conclusion is that the substitution of Fe atoms with Ni ones reduces the magnetic moments per Fe, Co and Ni atom. In effect the average magnetic moment per 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)


65

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 nuclear power industry and military nuclear pro-grammes are currently immobilised by vitrification. Borosilicate glass provides the very suitable medium for the majority of the species present in these wastes [1, 2]. It prevents leaching of radio nuclides by water- immobi-lisation effect. Environment protection legislation and increase of disposal costs makes the vitrification of the low level nuclear waste (LLW) favorable [3]. The treatment of such waste begins with reduction of their volume by incineration. The ash containing radio iso-topes, is suitable for vitrification and ceramization by incorporating it into the composition of boro-aluminosilicate glass, similar to that used in nuclear power industry.

Our studies concerned the influence of Cs as a characteristic component of ash after combustion of LLW on the structure and properties of borosilicate glass. The effect of introducing Cs2O or both Cs2O and CaO on the properties of boro-aluminosilicate glasses is little known, as the compounds are not used in tradi-tional glass manufacturing.

Four different compositions of glass were studied. (Table 1). CaO was present in glasses 1 and 2, and was added as the characteristic component of ash ob-tained from paper incineration. The other ash compo-nents: SiO2, Al2O3 were already present in the base glass (glass 3) composition. In two glasses a part of Na2O (5 mass %) was replaced by Cs2O (glass 2 and 4).

Table 1. The chemical compositions of investigated Glassem.

Chemical compositions

[mass %]

Glass 1

Glass 2

Glass 3

Glass 4

SiO2 48.5 48.5 56 56 B2O3 7.5 7.5 15 15 Al 2O3 8 8 8 8 CaO 18 18 - - Na2O 18 13 21 16 Cs2O - 5 - 5 Our results have shown that the introduction of

relatively small amount of Cs2O (5 % mass) instead of Na2O induces considerable changes in the structure and the thermochemical properties of boroaluminosilicate Na2O – B2O3 – Al2O3 – SiO2 glass. FTIR spectrum of Na2O – B2O3 – Al2O3 – SiO2 glass is characterized by an intensive band of Si – O – Si bridges of silicate net-work at 1000 cm-1, 729 cm-1, and a band 1407 cm-1 of [BO3] groups which occur in its structure. The band

connected with the cation modifier Na+ occurs at 458.8 cm-1. Introduction of Cs2O causes the shift of the main band to 1017cm-1 and the glass modifiers band to 455.9 cm-1. It means that the presence of Cs+ increases the degree of polymerization of the network. Introduc-tion of Ca causes the appearance besides of the Si-O-Si band (1021 cm-1) the band at 946 cm-1, which is charac-teristic for silicate and aluminate glasses, containing calcium. This indicates the formation in the network the domains containing Ca; also yielding the shift of the [BO3] band to 1422 cm-1. The band connected with the cation modifiers becomes shifted to 471 cm-1. This means that the presence of 5% mass of Cs2O, affects significantly the glass structure. The effect is stronger when Cs2O and CaO are introduced simultaneously; then the degree of polymerization of the silicate network increases producing the observed shift of the Si-O-Si band toward higher frequencies (from 1000 to 1021 cm-1).

Introduction of Cs into the basic glass Na2O – B2O3 – Al2O3 – SiO2 (waste glass) in order to immobilize its radioactive isotope induces changes in the structure and in the properties of the glass. This results from consid-erable crystallochemical differences between Cs+ and Na+ as the glass structure modifiers. In the presence of even a relatively small amount of Cs2O the degree of polymerization of the glass network as well as its stabil-ity increases. Evidently this means the increase of the chemical durability of the glass. On the other hand above glass transformation temperature (Tg), cesium acts as the strong depolymeriser, increasing the ten-dency for crystallization of the basic glass. It becomes incorporated into the structure of the newly formed crystal phases such as the chemically resistant alumi-nosilicates. Similar changes are induced by the introduc-tion of CaO into the glass. Our results confirm and ex-plain the suitability of borosilicate glass for inactivation of the incinerated hospital and laboratory wastes con-taminated with radioactive 137Cs [4].

References [1] W. Donald, Glass Technology: Eur. J. Glass Sci. Tech-

nol. A 48 155 (2007) [2] M.I. Ojovan, W.E. Lee, An Introduction to Nuclear

Waste Immobilisation, Elsevier Science,Amsterdam, (2005)

[3] I. A. Sobolev etal., Glass Technol., 46 28 (2005) [4] K.Choi et al., Waste Management 20 575 (2000)


66

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. Maurin 1, A. Krukowski, Z. Czarnocki 1

1Institute of Atomic Energy 2University of Warsaw, Department of Chemistry, Warsaw, Poland

Asymmetric transfer hydrogenation (ATH) has be-come a highly powerful, versatile and practical tool for stereoselective synthesis of non-racemic secondary alcohols and amines from their prochiral substrates such as ketones or imines. Several effective ligands have been introduced, including a variety of β-amino alcohols and 1,2-diamino compounds [1,2,3,4]. These ligands form coordinatively saturated 18-electron chiral Ru(II) complexes when reacted with a ruthenium pre-catalyst, such as [RuCl2(η

6-mesitylene)]2, that serve as promoters for stereoselective reduction of prochiral compounds with usually extremely high efficiency. The present study is a part of our programme aimed at the construc-tion of new ATH catalyst ligands. We report here the 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. 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

(O2) is active as an acceptor for two weak O1-H10···O2 and N2-H2B···O2ii hydrogen bonds, the first of them being intramolecular, whereas the second is an intermo-lecular bond. The remaining N1—H1···O3i

intermolecu-lar hydrogen bond links the sulfonoamide N1—H1 hydrogen and S1=O3 oxygen of adjacent twofold scre-waxis-related molecules. These chains of molecules, in the b-axis direction and visible easily in Fig. 2, are linked together by weaker N2—H2B···O2ii

hydrogen bonds, forming sheets of molecules parallel to (110). The in-plane molecules are arranged so that their hydro-phobic parts point towards the surface. The interior of such sheets has more hydrophilic character. The view of crystal packing is shown in Fig. 2.

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)


67

SYNTHESIS AND ANTI-HIV STUDIES OF 2-ADAMANTYL-SUBSTITUTED THIAZOLIDIN-4-ONES

J. Balzarini1, B. Orzeszko2, J. K. Maurin 3, 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 a wide range of biological activities including antibacte-rial (inhibitors of the bacterial enzyme MurB) [1], anti-tuberculosis [2], antitumor [3], antihistaminic (H1 an-tagonist) [4], and anti-inflammatory (COX-1 inhibitors) [5] or anticonvulsant activity.

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-zolidine ring, were synthesized. It was found that sev-eral compounds exhibited a modest anti-HIV-1 activity, while (±)-2-adamantan-1-yl-3-(4,6-dimethyl-pyridin-2-yl)-thiazolidin-4-one 22 was endowed with a remark-able antiviral potency (EC50 = 0.35 µM) [7]. The ada-mantane moiety played an important role in an eventual antiviral activity of the compound. This compound behaved as a typical non-nucleoside reverse transcrip-tase (RT) inhibitor with non-competitive inhibition against RT with respect to the substrate (Ki = 12 µM). For this compound separation of the enantiomers via diastereoisomeric salts was performed. X-ray studies taking into account anomalous dispersion effect [8] enabled us to ascribe the S configuration to (–)-2-adamantan-1-yl-3-(4,6-dimethyl-pyridin-2-yl)-thiazolidin-4-one (-)-22. Furthermore, it was found that

the (+)-22 isomer was responsible for the most potent anti-HIV-1 activity with an EC50 value of 0.178 µM, while the levo isomer was over sixty-fold less active. The obtained from the X-ray studies molecular structure of the camphoresulphonic acid salt of (-)-22 is shown in Fig. 1.

Fig. 1. The molecular structure of the camphoresulphonic salt of (-)-22. The independent part of the unit cell consist of the amine cation part and the camphore sulphonic acid anion. The non-hydrogen atoms are shown as 30% probability ellipsoids.

References [1] C. J. Andres et al., Bioorg. Med. Chem. Lett. 10 715

(2000) [2] K. Babaoglu et al., Bioorg. Med. Chem. Lett. 13 3227

(2003) [3] S. Grasso et al., Farmaco 43 851(1988) [4] M. V. Diurno et al., J. Med. Chem 35 2910 (1992) [5] G. C. Look et al., Bioorg. Med. Chem. Lett. 6 707

(1996) [6] A. Rao et al., Antivir. Res. 63 79 (2004) [7] J. Balzarini et al., Eur. J. Med. Chem. 42 993 (2007) [8] H.D. Flack, Acta Cryst. A39 876 (1983)


68

ENERGY DECOMPOSITION ANALYSIS AND ECTRON DENSITY CHARACTERIZATION OF HETEROCYCLIC DIMERS

INTERMOLECULAR INTERACTIONS B. Paluchowska


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. 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 carboxylic acid dimers to -18,95 kcal/mol in the case of furancarboxylic acid dimers.

Much weaker, but also significant interactions, are stacking forces between heterocyclic rings (π-π interac-tions of energy from -6,27 to -3,84kcal/mol)-. Fig. 2.

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. 3. C-H…π interactions. Cutoff is at 0.025 e/bohr3; contour-line spacing is 0.001 e/bohr3.

The attractive interaction in the perpendicular ar-rangement (Fig. 3) is the cause source of preference for the herringbone structure in real crystals of the studied molecules.


69

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 constructed for the dimeric motifs of furancaroxylic acids (2- and 3-FCA), and thiophencarboxylic acids (2-and 3-THCA) to visualize the interactions between molecules. Their characteristics served to encode differ-ent structural properties and intermolecular contact distances.

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 surface are a function of the closest distances from the point to a nuclei inside and outside the surface. In this manner all interaction types (hydrogen bonding, close and distant van der Waals contacts, C–H···π interactions, π – π stacking) are readily identifiable, and it becomes a straightforward matter to classify molecular crystals by the nature of interactions, when examining crystal pack-ing diagrams.

In order to visualize the properties of the a mole-cule on the Hirshfeld surface the two parameters de and di are defined - de is the distance from the Hirshfeld surface to the

nearest nucleus outside the surface - di is the corresponding distance to the nearest nu-

cleus inside the surface.

The de.and di reflect the most immediately useful property to map onto the surface.

Where atoms make intermolecular contacts closer than the sum of their van der Waals radii, these contacts will be highlighted in red on the di and de surface This property provides an immediate picture of the nature of intermolecular contacts in crystal.

Fig. 2. Fingerprint plot produced from the Hirshfeld surface on 2-FCA molecule representing C-O contacts.

The Fig. 2. shows fingerprints of C-O kind of in-teractions within the examined dimmers. These kind of plots correlate their several most obvious features with short and long intermolecular contacts within the crys-tal. The stripe roughly along the diagonal reflects a large fraction of points on the Hirshfeld surfaces that involves nearly head-to-head H···H contacts (i.e. a nearly linear C–H···H–C orientation) between neighbouring mole-cules.

References [1] F.L. Hirshfeld, Theor. Chim. Acta, 44, 129 (1977) [2] M. A. Spackman, J. J. McKinnon, CrystEngComm, 4,

378 (2002) [3] S.K. Wolff, et al., CrystalExplorer 2.0 program


70

DIFFRACTION DATA AND MICROSTRUCTURE OF Al2O3 – SiO2 COATINGS

L. Górski 1, A. Pawłowski2 1Institute of Atomic Energy

2Institute of Metallurgy and Material Science PAS, Kraków, Poland

The recent studies concern coatings of thermal bar-rier type containing composites belonging to the system Al 2O3 – SiO2 system. In this system only one common phase - mullite, with the approximate formula 3·Al2O3 – 2·SiO2, exists [1]. Mullite crystallizes in the orthorhom-bic system with the lattice parameters: a =7.546 Å, b = 7.690 Å, c = 2.884 Å, and the space group – Pbam [2].

X-ray diffraction patterns determined before and after plasma spraying are consistent with the mullite structure. One can observe, however, some differences in several peak intensities which may result from polytypism. Intensities on the coating pattern (Fig. 1b) are closer to those given in [2].

a

0

50

100

150

200

250

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

2 theta

co

un

ts

b

Fig. 1. Diffraction patterns Al2O 3 – SiO2 composite, Cu radia-tion;a -powder before spraying, b- coating as sprayed.

The coating structure in nanometric scale was stud-ied by transmission electron microscopy (TEM) com-bined with electron diffraction on selected areas. Specimens are were prepared by focused ion beam mill-ing. The existence of alternate layers amorphous, nano- and polycrystalline layers has have been observed. Amorphous layers are were visible near the metal – ceramics boundary (Fig. 2). The electron diffraction

pattern (Fig. 2b) corresponds to the area marked on the microscopic image (Fig. 2a).

In the coating body mainly polycrystalline layers with some local discrepancies in chemical and phase composition are observed. These effect due to plasma spray process conditions, which are far from the ther-modynamic equilibrium.

The microstructure observed for coatings contain-ing Al2O3 – SiO2 composites is similar to that found in previously studied coatings based on Al2O3 and ZrO2, though with some remarked differences [3,4].

Further studies aimed at the detailed description of the coatings’ morphology and its dependence on ther-mal treatment are still in progress.

a

b

Fig. 2: a – TEM image from an area near the ceramics-metal boundary, b – electron diffraction pattern from the area D marked red in (a)

References [1] R.F. Davis, J.A. Pask, J. Am. Cer. Soc., 55 525 (1972) [2] Powder Diffraction File System, Ver. 2.2, 15-776 [3] A. Pawłowski et al., Arch. of Metallurgy and Materials,

47 400 (2002) [4] L. Górski, A. Pawłowski, Solid State Phenomena, 130

297 (2007)

D


71

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-acteristics of metals and alloys are hard to achieve by using implantation techniques at moderate doses. Such a problem arises, when one tries to improve thermal sta-bility of the manganin based high-pressure sensors [1]. In our research the pressure and temperature sensitivi-ties of manganin foil after high-dose implantation with 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 established with the reliability much beyond the error bars. First, the pressure sensitivity increased from α = (2.45±0.01)·10-5 MPa-1 before implantation to αimp = (4.60±0.01)·10-5 MPa-1 after implantation with 250 keV Kr at the dose of 1016 ion/cm2. Second, the appreciable reduction of the temperature sensitivity of manganin as the high-pressure sensor was attained [4].

The reduction of the temperature sensitivity can be described as decrease of a coefficient in the simplified

description of the temperature dependence of the sample electrical resistance:

( )[ ]2max max

1 TTaRR R −+=

yielding broader maximum that occurs in R dependence on T.

Fig.1. Qualitative picture of the temperature dependence of the absolute value of the deviation of the manganin sample resistance from the maximum.

References [1] B. Słowiński, R. Wiśniewski, JINR Comm. E14-89, 512

1-6, Dubna (1989) [2] B. Słowiński et al., Nukleonika, 44 227 (1999) [3] T. Wilczyńska et al., Vacuum 78 515 (2005) [4] R. Wiśniewski et al., Vacuum 81 1199 (2007)


72

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-provement of the thermoresistance properties of man-ganin gauges by ion implantation. The studied samples were 20 Ω gauges produced by Dynasen Corp. in the form of planar structures containing of 2.5 µm thick manganin layer [1]. The manganin layer was initially implanted with 60keV energy Ti ions (1016 cm-2) and then with 250MeV Kr ions (1013 Kr cm-2). The maxi-mum penetration range of Ti ions estimated with the TRIM code is 50nm. In the Kr ion implantation a 13µm thick special protection foil was used. The TRIM calcu-lations indicate that Kr ions are distributed uniformly with density of 4·1018cm-3 all over the manganin layer. We have assumed that during Kr implantation the Ti ions were transferred deep into the manganin layer up to a depth of 0.5µm. The implanted sample can be mod-eled by two adjacent layers: the 0.5µm thick surface layer with high Ti atoms content and the 2µm thick one containing Kr atoms.

Fig. 1. Model of ion distribution in implanted manganin sam-ple.

The temperature behavior of the electrical resis-tance of the Dynasen gauges before and after ion im-plantations was studied for temperatures within the 20 - 220ºC range (Fig. 2). The resistance of Dynasen 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 smaller electrical resistivity than the layer containing only Kr atoms. Using our model of the sample (Fig. 1), we found that the electrical resistivity of the material 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

resistivity of manganin implanted with Kr ions increases by 10% [2].

0 50 100 150 200Temperature [°C]

21

21.1

21.2

21.3

21.4

Res

ista

nce

[Ω] non-implanted

a

0 50 100 150 200Temperature [°C]

19.50

19.55

19.60

Re

sist

an

ce [Ω

] Ti+Kr implanted

b

Fig. 2. Temperature dependence of the Dynasen manganin gauges resistance before and after ion implantation.

Since the concentration of the Kr and Ti atoms in implanted layer is very large ~1022 cm-3, one can expect significant changes in other characteristics of the sam-ple. Further studies will concern the pressure and strain sensitivity of implanted gauges.

References [1] T. Wilczyńska, R. Wiśniewski, unpublished [2] T. Wiczyńska et al., Vacuum, 78 515 (2005) [3] R. Wiśniewski, T. Wilczyńska, Materials Science 13 10

(2007)


73

HIGH PRESSURE EFFECTS IN CASTOR AND RAPE OIL R. Wiśniewski, T. Wilczyńska


Almost twenty years ago the new high-pressure castor oil phase has been discovered [1] and quite re-cently the similar phase was found for rape [2] and soy [3] oil. The oils are composed of triglycerides of differ-ent fatty acid (triacylglycerols) and their molecules are of rod-shaped. Their phase diagrams plotted in the tem-perature – pressure plane contain the specific region where the change to a high pressure phase is possible (Fig. 1).

-40 -20 0 20 40T [°C]

0

0.5

1

P [G

Pa]

LIQUID

SOLIDHP phase

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 oil density after the high pressure phase might account for the observed change in the light transmittance.

In order to study the possible changes in chemical composition of the oil samples during pressure treat-ment various high efficient chromatography methods (GLC, HPLC-PR and HPSEC) were used. Slight de-crease (from 83.63 to 82.61%) in the content of the main component was found.

The Raman spectra investigation for castor oil re-vealed a change of 3931 cm-1 line. However, no such change in the rape oil Raman spectra was observed.

0

20

40

60

80

100

300 500 700 900 1100

wave length(nm)

tran

smit

tan

ce(%

)

Fig. 2. The light transmission spectra for castor (red) and

rape oil (blue). The lower curves refer to the samples before the high pressure treatment.

The very large hysteresis in volume change is ob-served during pressure changes for castor oil. Similarly, in the case of rape oil after the first cycle of investiga-tion no reversible change in volume were noticed (Fig. 3).

Fig. 3. Relative volume changes of rape oil during the pres-sure cycle from normal conditions followed by increase in pressure (370 MPa, 48h) to induce the phase transi-tion, and then decrease of pressure to normal condi-tions.

References [1] M. Siegoczyński et al., High Pressure Res. 1, 225

(1989) [2] A. Rostocki et al., J. Mol. Liq., 135 120 (2007) [3] A. Rostocki et al., High Pressure Res., 27 43 (2007)


74

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 ion beam extraction is indispensable in applications like ion implantation, lithography, micro-analysis, plasma heating, ion thrusters and many others.

The beam extraction is commonly described with the Child-Langmuir ’’3/2’’ formula, derived for flat electrodes diode [1]. The formula has been modified for spherical and cylindrical systems [2], and corrections for the initial velocity have been introduced [3]. Al-though, the Child-Langmuir formula describes properly charge limited flows [4], it neglects many important factors like variable area and shape of the plasma me-niscus; focusing effect of the meniscus; limitations of the ion flow into the extraction area caused by finite plasma density; geometry of extraction hole. All of the factors may cause deviations from ’’three halves’’ law like linear current-voltage dependence [5] or the current saturation [6].

In our study we have employed the TRQR code [7] based on the particle-in-cell (PIC), to simulate the beam extraction process in simple model of hollow cathode ion source. The code treats charged particle behavior in a self-consistent manner, taking into account space-charge of plasma and extracted beam. Plasma meniscus formation, evolution of potential distribution and cur-rent-voltage curves were studied.

0 2000000 4000000 6000000 8000000 10000000

0

100

200

300

400

r = 4 mm

r = 5 mm

I [a.

u.]

U3/2 [ V3/2 ]

r = 6 mm

Fig. 1. Current-voltage curves for different hole sizes.

Simulations were peerformed for different: diame-ters of extraction hole, extraction electrode–extraction hole distances and plasma temperatures. Current-voltage curves of the form I~U3/4 were obtained (Fig. 1). The dependency of plasma meniscus surface and shape on extraction voltage were also investigated (Fig. 2).

0 10 20 30 40 500

1

2

3

4

5

6

7

8

9

Sm

[ m

m2 ]

Ue [ kV ]

simulation fit

y(x) = a+b*x1/2

a = 0.89

b = 1.09

Fig. 2. Plasma meniscus surface as a function of U.

The calculated current-voltage characteristics are not linear in the (U3/2,I) coordinates. The deviations from the ’’3/2’’ law can be desribed by the dynamical perveance defined as:

( )2/3/ UddIPd =

The dependence of Pd on U yielded by the simula-tions is very similar to that obtained from experimental measurements [8,9].

0 2000000 4000000 6000000 8000000 10000000 120000000.00000

0.00005

0.00010

0.00015

0.00020

U3/2 [ V3/2 ]

Pd

[a.u

.]

r = 4 mm r = 5 mm r = 6 mm

d =10 mm

Fig. 3. The dependence of perveance Pd on extraction voltage.

References [1] H. Zhang, Ion Sources, Springer, Berlin (1999) [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

(1961) K. Shinto et al., Rev of Sci Instr, 77 512 (2006) [5] M.C. Vella et al., Ion Implantation Technology 5 27

(2000) [6] P. Suominen et al., Proc. of the 15th Int. Workshop on

ECR ion sources, Jyväskylä, Finland, 12-14 June (2002) [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)


75

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 Ar+ bombarded Ti target has been studied. In experi-ments the system designed for medium energy ion beam sputtering was used [1,2]. The Ar+ kinetic energy varied in the range of 20-30 keV. The primary beam current density was 0.7 µA/cm2

The secondary ions energy spectra determined for different values of the voltage, Ue, between the target and energy filter entrance is a smooth single-maximum distribution (Fig. 1). The expected increase of the sec-ondary ions current with increasing Ue is also observed (Fig. 2).

0 50 100 150 2000

250

500

750

1000

3

I j[pA

]

E [eV]

30 keV Ar+ Ti1) Ue=60V

2) Ue=80V

3) Ue=100V

1

2

Fig. 1. Energy spectra of secondary ions emitted from Ti target irradiated by Ar+ beam.

40 60 80 100 120 140 160 180 2000

200

400

600

800

1000

1200

1400

1600

Ar+ TiI max

[ p

A ]

Ue [ V ]

20 keV 30 keV

Fig. 2. The dependence of maximal secondary ion current on extraction voltage.

The energy spectra of secondary electrons emitted from titanium target for different energy of incident Ar+ ions are also one-maximum distributions (Fig. 3). The measurements of the dependence of the secondary elec-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.

One aim of the study was to determine the optimal Ue value for the best resolution measurements of secon-dary ion mass spectra. The optimal Ue value results from secondary ion current – mass spectrum resolution trade-off.

0 20 40 60 80 100 1200

20

40

60

80

100

120

140

160

180

200

20 kV

I e [

pA

]E [eV]

Ar+ Ti

30 kV

Fig. 3. Energy spectra of secondary electrons emitted from Ti target.

Since titanium has five well-distinguishable iso-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 ion current was achieved for Ue = 90 V (Fig. 4).

44 45 46 47 48 49 50 51 520.00E+000

5.00E-010

1.00E-009

1.50E-009

2.00E-009 20 keV Ar+ -> Ti

I j [

A ]

m [ j.m.a ]

Ue= 120 V

Ue= 110 V

Ue= 100 V

Ue= 90 V

Ue= 80 V

Fig. 4. Mass spectra of secondary ions.

Similar studies have been performed for Si targets [3].

References [1] A. Drozdziel et al., Rapid Commun. Mass Spectrom.20

298 (2006) [2] K. Pyszniak et al., Vacuum 81 1145 (2007) [3] K Pyszniak et al., Elektronika 10 51 (2007)

ANNUAL REPORT 2007 Nuclear Techniques in Health and Environment Protection

Management of Hazards

79

CENTRE OF EXCELLENCE MANHAZ – MANAGEMENT OF HEALTH AND ENVIRONMENTAL HAZARDS

The EU Centre of Excellence MANHAZ (Man-agement of Health and Environmental Hazards) was established in 2003 in the Institute of Atomic Energy in Świerk.

The mission of the Centre of Excellence MANHAZ is to provide leadership, expertise and inte-gration of efforts related to risk assessment of activities involving hazardous substances in Poland. The main areas of activities CoE MANHAZ cover variety of problems related to development and practical imple-mentation of recommended methodologies, procedures guides, computer programs and data bases for the fol-lowing four groups of problems:

1. Management of major accident hazards – advanced tools and information systems for supporting au-thorities in the management of risks and emergency situations due to technological hazards.

2. Management of chemical hazards relating to emis-sion of chemicals, their transport and transforma-tion in the environment, environmental and health risk assessment: models, data bases, stand alone computer programs and systems for health and en-vironmental risks assessment and decision making.

3. Risk assessment of fuel cycles of electrical power generation, including externalities.

4. Tools for radiological risk assessment and decision making for close and distant accidents.

The Centre is getting involved in a number of pro-jects on infrastructure security management in Poland. In particular it concerns: - development of computer aided decision support

system for crises management in the agglomeration of Warsaw;

- customization of existing methodologies for securi-ty vulnerability assessment of chemical installa-tions in Poland;

- GIS based decision support systems for crisis ma-naging chemical, radiological or terrorist emergen-cies – cooperation with the National Defence University.

In 2007 one of the most important tasks of the Centre was related to the participation in the national project on: Hazard models for urban agglomeration and crisis management system exemplified by the city

Warsaw. The consortium of institutions began realisa-tion of the project in the mid of 2006. The Institute of Atomic Energy is responsible for two parts of the sys-tem dealing with modelling of radiological and chemi-cal. The radiological part is being implemented jointly with the Material Research Laboratory of the Institute of Atomic Energy.

The main objective of the project is the deve-lopment of a prototype of the new advanced, integrated system of modules and data that:

- determines emergency zones based on simulations of the dispersion of hazardous nuclear, biological, and chemical materials released to the atmosphere and water bodies in urban areas,

- provides essential information on required resour-ces, such as search and rescue teams, equipment, medical assistance, food, evacuation and shelter, needed in case of emergency situation,

- has access to all the necessary databases and GIS-based information, which can be distributed geo-graphically among different urban services,

- enables co-ordination of emergency action in real-time based on reliable system for information ex-change and interoperability capabilities among different systems.

The MANHAZ Centre acts also a Technical Support Organization for the Centre for Radiological Events of the National Atomic Energy Agency and is involved in the integrated project EURANOS “Europe-an approach to nuclear and radiological emergency management and rehabilitation strategies”.

The staff of the Centre has been also engaged in the development of environmental systems for man-agement of air quality.

References [1] MANHAZ Monograph, Models and techniques for

health and environmental hazard assessment and man-agement, Otwock (2006)

[2] M. Borysiewicz et al., IAE Report B–30 (2006) (in Polish)

[3] M. Borysiewicz et al., IAE Report B–31 (2006) (in Polish)

[4] M. Borysiewicz et al., IEA Report B–22 (2007) (in Polish)

Nuclear Techniques in Health and Environment Protection ANNUAL REPORT 2007


80

SYSTEM SECURITY RISK ANALYSIS M. Borysiewicz


The industry and operators of various element of critical infrastructure face the important need to assess whether current security measures effectively address the new and unforeseen threats, and make enhance-ments as required to provide for the safety of the public, workers, and the environment. Security risk manage-ment involves the systematic identification, analysis, treatment (e.g., mitigation, acceptance, transfer), moni-toring, and communication of risk. Key components of a security risk management process are risk analysis, in which a system, its components, and their relationships are analyzed with respect to threats and vulnerabilities; risk assessment, in which the level of risk is determined based on analysis and a well-defined approach to identi-fying and assigning values to risk factors, including possible consequences or impacts of threats; and risk communication, in which the results of a risk as-sessment are translated into terms that are meaningful to decision-makers.

Security incidents are intentional, rather than acci-dental, which is a key basis to understanding the haz-ards, likelihood, and possible consequences. The risk that is being analyzed to solve security issues is an expression of the likelihood that a defined threat will reach a specific vulnerability of a particular attractive target or combination of targets to cause a given set of consequences.

The estimate of consequences may be different in magnitude or scope than is normally anticipated for accidental releases. In the case of security events, ad-versaries are determined (sometimes at all costs) to find vulnerabilities and to maximize damage. In addition, theft or diversion of chemicals is normally not conside-red in accidental release studies, but should be included in security studies.

A second unique term of interest is vulnerability, which is any weakness that can be exploited by an ad-versary to gain unauthorized access to an asset. Vulner-abilities can result from, but are not limited to, man-agement practices, physical security weaknesses, or operational factors.

A variety of approaches to system security risk analysis and risk assessment have been taken:

Policy-based approaches focus on security requ-irements, as stated in organizational Policy documents, or in applicable regulations or standards. Failure to meet a requirement – typically, to implement a specific safeguard – constitutes a potential source of risk. In a policy-based approach, the consequences of such a failure are analyzed and assessed.

Threat-based approaches focus on how an adversa-ry could exploit technical aspects of a system (e.g., inherent vulnerabilities, poor configuration of key com-ponents), as well as non-technical aspects of the sys-tem’s operational environment, to produce adverse effects. Analysis, rather than assessment, predominates in a threat-based approach.

Asset-based approaches focus on the assets that must be protected from threats. An asset-based appro-ach includes identification of system components, as well as analysis of their interconnections and depen-dencies.

Mission- or objective-based approaches focus on the missions or business objectives that must be achieved, despite the presence of threats. A mission-based approach includes identification of business func-tions and how those functions relate to (e.g., depend upon, impose requirements on) systems and their be-havior.

The an analytical portion of these approaches is cal-led a Security Vulnerability Analysis (SVA). The lead-ing institutions and organizations (e.g. Center for Chemical Process Safety - CCPS) dealing with chemi-cal process safety) created the SVA methodology to help companies to evaluate the vulnerability of their chemical sites to terrorist attack or other malicious acts. Methods available to SVAs can have varying scopes, varying levels of detail, and utilize different methods.

The SVA approach can also applied to informa-tion/cyber security, where the objective of is to protect critical information systems including hardware, soft-ware, infrastructure, and data from loss, theft, or dam-age. In a chemical facility, protecting information and computer networks means more than safeguarding a company's proprietary information and keeping the business running, as important as those goals are. It also means protecting chemical processes from hazardous disruptions and preventing unwanted chemical releases. To an adversary, information and network access can provide the power to harm the company, its employees, and the community at large.

A analysis of SVA methodologies and approaches to SVA based security management in chemical process industry, the related information/cyber security and Industrial Control System were studied by the author, in the framework of the project on integrated methods for major accidents . risk and security implement in the period 2005- 2007 by the Central Institute of Labour Protection n Warsaw



81

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 by the Ministry of Science and Higher Education and implemented in the period 2005 -2007 by the Institute of Environmental Protection in cooperation with the Centre of Excellence MANHAZ in the Institute of Atomic Energy was to develop an integrated pollutant air concentration prediction system for urban agglom-eration (SPSZP-Ag) for predicting air quality, analyz-ing emission events and accidental releases and calcu-lating contaminant transport, including secondary con-tamination and analysis of selected areas, taking into account ozone, dust, NOx, SOx, heavy metals and haz-ardous substances. According to adopted assumptions, the SPSZP-Ag system was designed largely on the base of calculation systems developed for the U.S. Environ-mental Protection Agency, namely CMAQ (transport calculations and pollutant transformation in the atmos-phere) and SMOKE (source inventarisation and emis-sion calculations), as well as on the base of meteoro-logical models MM5 and WRF.

State-of-the-art solutions for emission and trans-port modelling and pollutant transformation calculation systems, as well as solutions for space information techniques and integration of calculation models were implemented during the development of the SPSZP-Ag system. The prototype software for the SPSZP-Ag sys-tem was implemented on the Beowulf cluster running under the Linux operating system in the Centre of Ex-cellence MANHAZ and using the MPI package for parallel computing.

The following five subsystems were developed in the frames of the SPSZP-Ag system. Two versions of emission modelling subsystems: an advanced one (EMS/SMOKE) (1) basing on the concepts and struc-ture of SMOKE and a simplified one (2), better suited for the present Polish emission inventarisation prac-

tices. The subsystems were developed for processing raw emission inventarisation data into input for given computation grids for further processing in the atmos-pheric pollutant transport and transformation modelling subsystem; A meteorological modelling subsystem (3), implementing MM5 and WRF models for mezoscale and local meteorological parameter forecasting, taking into account the characteristics of urban areas; A trans-port and transformation modelling subsystem PMTTZ/CMAQ (4) simultaneously taking into account many pollutants in air in many space scales, including the urban agglomeration scale, enabling the simulation of all important chemical and physical processes influ-encing the transport, transformation and deposition of pollutants in air using emission in meteorological mod-els and adapting tools for microscale calculations (ENVI-met model) and for the pollutant transport for street canyons (OSPAM program); An urban commu-nity health hazard estimation subsystem PON/APEX, linked with PMTTZ/CMAQ (5). The subsystem is based on the Pollutant Air Pollutants Exposure model ( APEX) developed for the US EPA. The SPSZP-Ag includes IO/API tools for input and output processing and for calculation results visualization (PAVE).

The SPSZP-Ag system enables to simultaneously analyze emissions and transport for many pollutants in many space scales (from local to urban agglomeration to regional), taking into account the coupling of trans-port models and chemical transformations to the dy-namics of the atmosphere. SPSZP-Ag was used to simulate the pollutant distribution in air for selected emission scenarios in the Warsaw agglomeration using emission data delivered by the Mazovian Voivodeship Environmental Protection Inspectorate. More informa-tion on SPSZP-Ag is available at the Web site: http://www2.cyf.gov.pl/spszp-ag.



82

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 a project aiming at the development of system for ma-nagement of crisis situation arisen due to chemical or radiological releases in urban areas [1].

A general concept for developing modules for chemical and radiological emergencies is based on the following assumptions: - the main aim of the simulation modules of chemi-

cal and radiological emergency situation is deter-mining emergency zones, taking into account po-ssible consequences for various types of hazards,

- the simulators to determine emergency zones should be as fast as possible.

Therefore the main idea is to include as many ele-ments of the system as possible into databases from which they can be fast and easily extracted. To meet these requirements, the system should contain as many pre-defined scenarios as possible. In case of real emer-gency these scenarios have to be adapted taking into account the current conditions. Such an approach ena-bles fast estimation of emergency zones, however with possible lost of precision. Nevertheless in emergency response context the most important is to determine the areas where some countermeasures like evacuation or sheltering have to be applied as fast as possible. Secon-dly the databases will contain also information related to decision making process like pre-defined tasks for rescue teams linked to appropriate templates of crisis situation. This will allow building step by step knowledge database, causing that the system can evolu-tionally change its character from typical “command and control” type to the expert system.

Then for each type of hazard it is necessary: - to develop simulation module to make prognosis

of the situation, - to include into databases data requested to perform

simulations, - to define decision templates and tasks for any

rescue teams and urban services.

Such a general approach allows for generalization and unification of the logical model and utilization of some formal programming techniques.

The implementation of the subsystem for chemical emergencies will be based on the following elements: - databases of physical-chemical substances, - intervention levels linked to substances database, - basic scenarios for selected substances or groups

of substances depending on the type of release, storing and transportation conditions,

- adaptive part of scenario depending on meteorolo-gical conditions and localization of source of rele-ase,

- emergency simulator, - simulation results presented on digital maps in the

form of emergency zones.

The basic scenarios will be calculated using either the Unified Model for Pollutant Dispersion in Atmo-sphere (UPDMA) or well known Hazard Prediction and Assessment Capability (HPAC) code. In principle the basic approach is similar to that one used in the Off-site Consequence Analysis Guidance for the Risk Manage-ment Program, however it is significantly extended to much greater number of different scenarios. All the results of pre-calculated scenarios with different mete-orological conditions taking into account a number of special parameterizations for urban agglomeration will be stored in databases. It is also planned to carry out CFD (Computational Fluid Dynamics)calculations for a set of particularly vulnerable locations of Warsaw in order to verify the simplified approach.

The proposed approach depends on two factors: - the proper choice of basic scenarios (in particular

how many pre-calculated cases should be included into database),

- the proper identification of crisis situation which corresponds to good parameterization of pre-defined scenarios.

The solution is to build gradually huge enough da-tabases, which will be useful in the future. Analogously approach will be applied for the radiological part of the system.

References [1] M. Borysiewicz et al., IAE Report B–22 (2007)

(in Polish)



83

SPATIAL PLANNING OF PREVENTING AND ABATEMENT MEASURES

IN THE CONTEXT OF MAJOR ACCIDENTS M. Borysiewicz


The report on “Spatial Planning of Preventing and Abatement Measures” [1] with recommendations on Spatial Planning Measures and Land Use Plans fo-cusing on issues of major industrial accidents was pre-pared by M. Borysiewicz as a part of his involvement in the Rivershield Project [2] coordinated by the Institute of Environment Protection in Warsaw. The RIVER SHIELD Project is implemented under the EU Com-munity Initiative INTERREG III B CADSES Neighbourhood Programme by the Institute of Envi-ronmental Protection (IEP) from Warsaw. The subject of the Polish part of this Project is the Oder River (the Odra River) in the Lubuskie Region. It is expected that the project will strengthen the capacity of emergency and environmental services engaged in the process directed at the reduction of the effects of potential indu-strial accidents.

The report [1] consists of the Guidelines for Land Use Planning in the context of the Seveso II Directive and 4 attachments: A. Relevant Steps in Major Accidents Quantitative

Risk Assessment Process. B. Environmental Risk Assessment. C. HSE's Current Approach to Land Use Planning

(LUP) Policy and Practice. D. Planning Assessment Method Using Sensitivity Levels

and 2 D Decision Matrix for Land Use Planning.

The Guidelines cover the following important top-ics: role of land use planning in major accidents risk management, principles and consideration of additional technical measures, hazard and risk assessment meth-odologies and criteria, database of land use planning scenarios and risk assessment data, modeling and end-points as well as environmental risk assessment meth-ods.

The experts from the Lubuskie Region prepared an expertise on “Risk Analysis of the Major Industrial Accidents in the Lubuskie Region as the Element of the Documentation concerning the Spatial Planning”, which together with the report on “Spatial Planning of Preventing and Abatement Measures” will provide rationales for proposals of modification of current land use plans in the Lubuskie Region in Poland.

References [1] M. Borysiewicz, Spatial Planning of Preventing and

Abatement Measures, Institute of Environmental Pro-tection, Warsaw (2007)

[2] M. Borysiewicz, W. Kacprzyk, The RIVER SHIELD Project – management of the risk form industrial water pollution, Environmental Protection and Natural Re-source, ser. 30 (2006)

[3] M. Borysiewicz, Proc. of International Seminar on Industrial Accidents, 25-27 September 2007, Ustrzyki Dolne – Jedlicze, Poland



84

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: http://manhaz.cyf.gov.pl/manhaz/ind.php?ff=projects are the main tangible results of the project TW6-TRE-DICNT implemented in Centre of Excellence MANHAZ.

The contents of the technical report covers the fol-lowing groups of problems:

• Inventory of International Nonproliferation Or-ganizations & Regimes: International treaties; Treaties, conventions & agreements related to the IAEA´s work; Treaties, conventions & agreements under IAEA auspices; Safety & Security; Science & Technology; Safeguards & Verification; Or-ganization & Cooperative Agreements.

• The safeguards system of the International Atomic Energy Agency including: Legal Basis of Agency Safeguards; Evolution of the Safeguards System 1991 – 2005; Measures to Strengthen the Safe-guards System, 1991-2005.

• Problems of safeguards system implementation. • Safeguards current status. • Financing IAEA verifications of the NPT. • Cost of implementation of nonproliferation regime

in states including: U.S. Financial Support to Meet Safeguards Obligations of IAEA; US FY 2006 Budget request for Defense Nuclear Nonprolifera-tion; Case of Poland.

• Expanding the nonproliferation regime on a diffe-rent financial basis. IAEA Safeguards expenditures and resources.

• EURATOM, including: Operation of the EURATOM safeguards office; EURATOM safe-guards resources (budget, staff resources and safe-guards equipment).

• FUSION energy, including externalities and proli-feration implications of thermonuclear-fusion energy systems: Risk assessment of fusion rese-arch; Technical points related to thermonuclear weapons and their proliferation; Nuclear Weapons Proliferation Issues of Thermonuclear-Fusion Energy Systems; Common proliferation implica-tions of all fusion energy systems; Neutron abun-dance: Fusion-fission hybrids and plutonium bre-eders; Tritium abundance: Boosted-fission and pu-re-fusion nuclear weapons; Dedicated nuclear we-apons materials production facilities; Latent ther-monuclear proliferation; Induced nuclear prolifera-tion; Specific proliferation implications of inertial confinement fusion (ICF): Nuclear weapon-effects research, Driving force of spin-off technologies, Declassification and latent proliferation.




85

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 contamination threat, the surface waters and the drink-ing water distribution system was considered [1]. The general approach to modeling of contaminations spreading in aqueous environment with one - and three-dimensional models was also outlined. The latter is based on the idea of THREETOX code [2] and its fur-ther extensions [3]. The code is used to simulate 3-D hydrodynamics fields, suspended sediment and toxicant transport. The code includes a set of sub-models. The hydrodynamics are simulated on the base of a three-dimensional, time-dependent, free surface, primitive equation model. The model equations are written in Cartesian co-ordinates. The water body is assumed to be hydrostatic and incompressible. The concept of eddy viscosity/diffusivity and Prandtls hypothesis with the variable turbulence length scale are used to define the turbulence stresses. At the free surface all fluxes (mo-mentum, heat, etc.) are prescribed. At the bottom and the land boundaries the conditions of no diffusive flu-xes of any property are used. The open lateral boundary conditions are modified radiation conditions.

Three-dimensional advection-diffusion equations are used to simulate the toxicant transport in the water column and an ordinary differential equation is applied to simulate concentration of a toxicant averaged over the thickness of an upper exchangeable layer of bottom deposition. The boundary conditions are: no flux of the toxicants concentration in solute and in the suspended sediments through the water surface, and its flux is

equal to the sum of fluxes of the particulate and diluted toxicants at the bottom boundary.

The models were applied to dispersion and trans-port calculations of oil and sulphuric acid spills to the Wloclawek reservoir.

The report [1] discusses also computer programs developed in the Centre of Excellence MANHAZ for determination of concentration of pollutants in surface waters basing on simplified numerical models recom-mended by International Atomic Energy Agency [3]. The last part of the report presents modeling systems for simulation of contamination dispersion in drinking water distribution net EPANET and EPANET-MSX, the latter is an extension to the original EPANET that allows it to model any system of multiple, interacting chemical species [5]. These models can be utilized by crisis centers for quick assessment of threats caused by release of toxic substances to potable water networks.

References [1] M. Borysiewicz et al., IAE Report B–52 (2007) (in

Polish) [2] N. Margvelashvily et al., Radiation Protection Do-

simetry, 73 177 (1997) [3] International Atomic Energy Agency, Safety Reports

Series, „Generic Models for Use of Assessing the Im-pact of Discharges of Radioactive Substances to the Environment”, Vienna (2001)

[4] MANHAZ Monograph, Part III, Otwock (2006) [5] EPANET 2 Users manual, EPA/600/R-00/57 (2000)



86

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 to be applied in urban areas either in case of accidental release of hazardous material into atmosphere or for examining air quality it is absolutely necessary to have accurate meteorological fields in highest possible reso-lution. This can be obtained by applying a limited area numerical weather prediction model. One the most popular and mature models is mesoscale model MM5 [1] developed by the Penn State University and NCAR consortium. In order to use this model for high resolu-tion simulations it is necessary to have detailed data on elevation, land use etc. and include special parameteri-zation. The data of the resolution of 1 km are available from the US Geological Survey. In order to evaluate different types of parameterizations which can be used in MM5 system CCU-CAML lidar measurements (in particular aerosol vertical profiles) performed at Ispra station (Italy) [2] were utilized. In such a way estima-tion of boundary layer could be done by means on me-asurement and compared with the predictions obtained from MM5 simulations.

A series of numerical simulations were performed to understand to which extent the lidar-detected evolu-tion of the particles distribution along the vertical could be explained by the boundary layer and/or horizontal transport processes. A particular stress was put on inve-stigation of boundary layer parameters. The conclu-sions of the simulations can be summarized as follows:

Using MM5 and available data sets it is possible to investigate local phenomena in the atmospheric boun-dary layer (like mountain breeze or ground inversion), but there are some obvious limitations related to the following aspects:

The best resolution of terrain, land use and vegeta-tion data sets is 30 sec, which correspond to about 0.9 km (at middle latitudes). Then 1 km grid size is a reasonable choice for high resolution calculations. This in turn means that it can be difficult to simulate some very local effects – like impact of the areas, which shape doesn’t suit very much to the grid (for example long and narrow lake).

There is a need for appropriate computer power as one can roughly estimate the time needed for making simulations on n nested grid as proportional to the num-ber of grid points times 3 to the (n-1) power. It should be also stressed that putting more advanced physics option makes it necessary to decrease time step to fulfil the Courant-Friedrich-Levy stability condition.

The MM5 modelling system has a possibility to include observation data using nudging procedure. In particular it could be of some advantage to add infor-mation on vertical profiles. The problem is however such, that requested data are often not available for the area of interest. In general coupling of observational data with high resolution numerical weather simulation is useful if the measured data have good frequency and come from at least a few stations in the domain. In this respect the drawback of used lidar station is that there are no nocturnal data.

References [1] G. Grell et al., A Description of the Fifth-Generation

Penn State/NCAR Mesoscale Model (MM5), NCAR/TN (1995)

[2] S. Potempski et al., Numerical weather simulations in support to the CCU CAML Lidar measurements: pre-liminary results for the case study of 21st September 2006 IES, Ispra, EUR 22855 (2007)



87

APPLICATION OF THE ENSEMBLE SYSTEM TO ANALYSIS OF ETEX EXPERIMENT

S. Potempski1,2, S. Galmarini2


The long-range tracer experiments ETEX [1], con-ducted in the autumn 1994, were organized jointly by the European Commission, the World Meteorological Organization and the International Atomic Energy Agency. Two different releases of passive tracers (PMCH and PMCP respectively), known as ETEX-1 and ETEX-2, took place in Rennes, France and a ne-twork of detection stations covering the area from Swit-zerland to Norway and from the United Kingdom to Poland was established to find concentration fields. Then a reliable set of measurement data was obtained, which can be used in the validation and evaluation of long-range atmospheric dispersion models. In 1999 the ENSEMBLE project [2] was set out to addresses har-monization and coherence issues for emergency man-agement and decision-making in relation to long range atmospheric dispersion modeling.

The participants of the ENSEMBLE project count most European Meteorological Institutes and national responsible emergency organizations in addition to Canadian, Japanese, Korean and US American agen-cies. The ENSEMBLE system can be seen as a web-based decision support system for real-time exchange and evaluation of national long-range dispersion fore-casts of nuclear releases with cross-boundary consequ-ences. The created datasets within the ENSEMBLE system can be statistically evaluated to generate various uncertainty measures of predicted concentrations. Apart from real-time exercises the ENSEMBLE group was also activated to perform simulations both for ETEX-1 and ETEX-2 experiments [3]. For the purpose of the analysis the results of the models’ simulation as well as measurement data were put on a regular geographical grid of 0.5o· 0.5o resolution and with 3h time step. Made in 2004, first analysis of the ETEX-1 experiment based on 16 models’ dataset by the means of the ENSEMBLE system, showed that the median of the distribution of models’ results (“median model”) gave better results than any other single model or average of the

ENSEMBLE models or any other percentile, in terms of statistical parameters (like factors of 2 or 5). Similar analysis, with 15 models’ datasets, was also made for ETEX-2 experiment. In comparison with ETEX-1, where a good agreement with measurement data was found, the analysis of the ETEX-2 case showed some essential discrepancies between the results of the mo-dels and observational data.

Additional analyses were also performed for a few weighted models obtained from both ETEX-1 and ETEX-2 datasets in addition to the median model. In particular the Bayesian Model Averaging (BMA) algo-rithm was applied to find the weights for the models, corresponding to the probabilities that the model is the closest one to the observation data. In these analyses 25 and 15 models’ results were used for ETEX-1 and ETEX-2 respectively.

Relatively good agreement has been found for the models based on the BMA schemes applied to two distinct ETEX experiments. Additional comparison have been made between the combined models created by the weights calculated in different manner: the BMA-based and the least square fitting with the avera-ge and two medians: the median obtained from the models’ results of the simulations and the median cal-culated using probability density function resulted from the BMA scheme. In general it can be stated that for emergency response purposes the median model can be considered as a reasonable compromise.

References [1] F. Girardi et al., (Eds), The ETEX project, EUR Report

181-43 EN, Luxembourg (1998) [2] S. Galmarini et al., Atmospheric Environment 38 4607

(2004) [3] S. Potempski et al., Multi-model ensemble analysis of

the ETEX-2 experiment, submitted to Atmospheric En-vironment



88

IMPROVING OFF-SITE EMERGENCY MANAGEMENT: DEMONSTRATION PROJECTS UNDER EURANOS FRAMEWORK

S. Potempski,1, 2, S.Galmarini2


The EU integrated project “European approach to nuclear and radiological emergency management and rehabilitation strategies” (EURANOS) was established to harmonize European efforts in improvement of off-site emergency in case of nuclear accident anywhere in Europe. The MANHAZ centre of the Institute of Ato-mic Energy acting as the Technical Support Organisa-tion for the Centre for Radiation Events of the National Atomic Energy Agency is also involved in the project. In 2007 a main demonstration subproject was entitled “ENSEMBLE evaluation of long-range atmospheric dispersion forecasts from national weather and predic-tion services”.

The purpose of all demonstration projects is also to engage National Emergency Centres using RODOS in specific exercises, where they could test both the func-tionality and the usability of RODOS for specific non NPP issues. The objective of the demonstration therefo-re was twofold, to gain the experience in operating and using RODOS for non NPP events and to provide fe-edback on both the usefulness and the improvements needed within RODOS.

The aim of the mentioned above subproject on op-erability of RODOS and ENSEMBLE systems was to demonstrate the adequacy of the ENSEMBLE approach and system to support the decision making in the early phase of an accident.

All the opinions and suggestions presented in the institutional reports have been grouped into the follo-wing categories:

1. Relevance of the dissemination of multiple model forecasts for emergency response.

2. Adequacy of the ENSEMBLE system for emer-gency management centres.

3. User interface, design, functionality. 4. Adequacy of the ENSEMBLE-RODOS interface. 5. Other aspects.

A special session of the ENSEMBLE system was organized for the demonstration project CAT2DEM02. All participating institutes received proper user ID and password to access this session. The session was a fully functional version of the ENSEMBLE system where the specific dataset for the demonstration were avail-able. By accessing the system each users had the possi-bility to operate the ENSEMBLE system with the tools using actual datasets as usually produced by the

ENSEMBLE modelling community and relating to a specific release case.

The ENSEMBLE system has been perceived by the participants of the CAT2DEM02 demonstration project as a very useful tool in supporting decision makers in case of nuclear emergency [1]. The multi-model approach is seen as relevant for emergency re-sponse because it can assist in producing more scienti-fically justified judgment on the radiological situation during such an event. In particular, verification of na-tional dispersion calculation results can be easily per-formed by the means of the ENSEMBLE system. Po-ssibility of detailed and objective comparison of diffe-rent models is a great value of the system. The informa-tion provided by the ENSEMBLE system can be very useful for early phase of the nuclear accident, essential-ly in case of the transboundary issues.

The system is seen as user friendly and easy to operate. Nevertheless the participants suggested some further improvements. Some of the proposed improve-ments are already in the new version of the system, which appeared in the meantime. For example, it con-cerns GIS-like approach for the presentation of the results in the system.

Some participants suggested also the need of more training before practical use of the system, as the sys-tem was originally designed for meteorological centres, where understanding of the ensemble methodology is higher than in emergency centres.

The most critical part of the system is related to the ENSEMBLE-RODOS interface. All the participants would like to have a possibility of calculating doses basing on the concentration fields available in the ENSEMBLE system. However, currently this interface can be treated rather as a premature prototype. Besides there are other unsolved elements, related to lack of consistency between both systems: ensemble approach for dealing with uncertainties is not incorporated into the RODOS system by any means.

Additionally some operational aspects should be solved in case of inclusion of the ENSEMBLE system into national emergency plans.

References [1] B. Tomic et al., EURANOS: Summary Report for

CAT2DEM02, EURANOS(DEM2)-TN(07)-01 (2007)



89

SECURITY OF INDUSTRIAL CONTROL SYSTEMS M. Borysiewicz


Recently, several factors have raised concern about the security of industrial control systems (ICS) which are key components of much of national critical infra-structures including the electric power, water and water treatment, oil and gas production and distribution as well as industrial and military manufacturing. First, there has been a general trend to replace specialized control devices, particularly controllers and communi-cations elements, with general purpose computer equ-ipment and associated data communications techno-logy. Second, many companies have chosen to inter-connect certain parts of their process control networks with their corporate intranet once they have introduced general-purpose equipment into the process control system.

To help industry address these issues, the National Institute of Standards and Technology (NIST) has initi-ated an industry wide group called the Process Controls Security Requirements Forum (PCSRF) [1]. The PCSRF is developing its security specifications using the Common Criteria (CC). The CC, ISO/IEC 15408 [2], is a meta-standard of criteria and constructs used to develop security specifications in support of the evalua-tion of products and systems. The specifications define and characterize the security problem including as-sumptions about the operational environment, threats that may be encountered and policies that must be en-forced. Also characterized is the intended approach to eliminate, minimize or monitor defined threats, and enforce stated policy.

The PCSRF has developed the Security Capabili-ties Profile (SCP) [3] as a first step towards develop-ment of protection profiles for industrial control sys-tems. (SPP-ICS) [4]. It is an extension of the ISO/IEC 15408 Common Criteria to support integrated systems.

The SPP-ICS specifies the integrated set of secu-rity requirements for industrial control systems. The integrated set of requirements includes requirements for operating policies and procedures, requirements for information technology based system components, requirements for interfaces and interoperability between

system components, and requirements for the physical environment and protection of the system. The goal of this aspect of analysis and design is to define security requirements for subsystems or system components at the lowest possible level while at the same time retain-ing the required level of assurance and security func-tionality for the integrated system as a whole. The secu-rity subsystem includes both the information technol-ogy based components and the non-information tech-nology based elements implemented via policies and operating procedures. Particular attention is given to the interaction and dependencies between the security subsystem and the overall industrial control system.

The System Target of Evaluation (STOE) deals with protecting data confidentiality, data integrity and system availability without interfering with safety sys-tem functions. Data integrity focuses on protecting data flows to and from the controller and the other ICS com-ponents or subsystems. The STOE is also intended to protect system availability to assure continuity of op-erations. The STOE consists of the security services and procedures, both automated and manual, which are designed to meet the security objectives defined to counter threats to the ICS. The recent work [5, 6] pre-sents the development of structured methods ICS secu-rity analysis including STOE framework.

References [1] Process Control Security Requirements Forum

(PCSRF) http://www.isd.mel.nist.gov/projects/processcontrol/

[2] Common Criteria for Information Technology Security Evaluation (1999)

[3] Security Capabilities Profile (SCP) (2003) [4] System Protection Profile for Industrial Control Sys-

tems (SPP-ICS) Version 0.91 (2004) [5] M.Borysiewicz, J.S.Michalik, Cybersecurity of indu-

strial control systems, Bezpieczeństwo Pracy, 10 8 (2007)

[6] M. Borysiewicz et al., Methodology of integrated risk assessment of major accidents and terrorist threats for chemical installations. CIOP-PIB, Warszawa (2006)



90

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-lence MANHAZ is acquiring the ability to calculate scenarios for crisis situation management for chemical and radiological emergencies, especially in urban areas. The main tool used for this purpose is the U.S. Defence Threat Reduction Agency’s Hazard Prediction and Assessment Capability (HPAC) code enabling the user to simulate risks arising from releases of dangerous substances to the atmosphere.

HPAC enables the calculation of a range of diffe-rent chemical/biological/nuclear (CBN) agent release scenarios, which include scenarios taking place: - in a chemical/nuclear/industrial facility, - in an urban environment, - during transport, - as a result of using a chemical/radiological weapon, - as a result of intercepting a missile with a CBN

load.

The scenario conditions can be set in great detail, taking into consideration many factors which may in-fluence the consequences of the release, including the description of the CBN agent used (species, quantity, container type, localisation) and its carrier, the localisa-tion of the event, current and forecast meteorological conditions, local topology, urban geometry and single building interior geometry. For the selected scenario HPAC provides calculated contaminant concentrations and risks as well as predictions of their dispersion in the environment. The MANHAZ implemented the HPAC code and carried out pilot calculations for several loca-tions in Warsaw to test the applications of the code. The report [1] describes the HPAC code possibilities and the work methodology and can be treated as a documentation for the Polish user of the code.

References [1] M. Borysiewicz, et.al., Report B–48 (2007) (in Polish)

PRESENTATION OF FLUENT PACKAGE CAPABILITIES M. Borysiewicz, Ł. Czerski, H. Wojciechowicz


The CFD (Computational Fluid Dynamics) pro-grams allow detailed calculational analysis of fluid flows in complex environment, eliminating the neces-sity of time-consuming and expensive experimental investigations during the design and modernization cycle of devices. The CFD programs allow to get the essential information about flow of liquid (the layout of velocity field, pressure field), the heat and mass transfer including chemical reactions.

The CFD models are used in industries including aerospace, automotive, chemical processing, power generation, heating, ventilation, air conditioning, bio-medical, oil and gas, marine and many others. From ventilation comfort in large buildings to the tiniest scale in micro-pumps and nanotechnology, a wide range of problems can be addressed due to the scalable nature of fluid dynamics. Specialized models for combustion, reacting flows and radiation, rotating machinery, elec-tronics cooling and many other applications, help provide the insight into equipment and processes requ-ired to increase production, improve longevity and decrease waste.

The application of Computational Fluid Dynamics (CFD) to the understanding of urban wind flow and dispersion processes has gained increasing attention

over recent years. While many of the simpler dispersion models are based on a set of prescribed meteorology to calculate dispersion, the CFD approach has the ability of coupling the wind field to dispersion processes. This has distinct advantages when very detailed results are required, such as for the case where the releases occur around buildings and within urban areas. CFD also has great flexibility as a testbed for turbulence models, which has important implications for atmospheric di-spersion problems.

The accurate prediction of the spread of dangerous substances is important for scenarios that help in pre-paring for possible attacks, as well as in the analysis and damage assessment that follows an event.

The IAE report [1] includes description of CFD package FLUENT adapted to cluster of computers in the Centre of Excellence “MANHAZ” enabling parallel processing and calculation examples.


(in Polish)



91

THE EXPERIMENTAL STUDY OF VOCs REMOVAL FROM EXHAUST GASES USING THE ELECTRON BEAM

FROM AN ACCELERATOR A. G. Chmielewski1, A. Ostapczuk1, J. Licki 2

1Institute of Nuclear Chemistry and Technology, Warsaw, Poland 2Institute of Atomic Energy

Volatile organic compounds (VOCs) are released into atmosphere from various industrial processes. The-ir main origins are: mobile sources, organic solvent application, petroleum industry, combustion of fossil fuels (industrial and non-industrial), waste treatment and disposal. Emission of VOC to the atmosphere can cause stratospheric ozone layer depletion, ground level photochemical ozone formation and toxic or carcino-genic human health effects. VOCs contribute to the global greenhouse effect. The reduction of VOCs emis-sion is of a growing concern of international conven-tions as well as EU Directives. The purpose of this project was to study the concentration of VOCs emitted from combustion of the light fuel oil Ekoterm-Plus (PKN Orlen, Płock) and their removal efficiency using the electron beam from an accelerator. The light fuel oil Ekoterm-Plus (Table 1) is commonly used for residen-tial heating in the municipal and living sectors in Po-land.

Table 1. Properties of light fuel oil Ekoterm-Plus.

Property Unit Value

Density at 15ºC kg/m3 830.8 Kinematic viscosity at 20ºC cSt 3.88 High heating value MJ/kg 42.6 Sulfur content % wt. 0.04 Water content % wt. 0.015 Ash content % wt. 0.002 Pour point ºC -30 Flash point C 66

The study was performed in the laboratory plant [1] at Institute of Nuclear Chemistry and Technology at Warsaw. The oil was burned by a Jet 4.5 EV burner. The obtained flue gas was irradiated in a process vessel (PV) by the electron beam from the ILU-6M accelera-tor. At the inlet PV, the sample gas was extracted for analysis of flue gas composition by two independent systems. The SO2 and NO/NOx concentrations were continuously determined by a set of two extractive gas analyzers The Model 10A/R (chemiluminescence NO/NOx analyzer) and the Model 40 (pulsed fluores-cent SO2 analyzer), manufactured by the Thermo Envi-ronmental Instrument Corporation (USA).

Organic pollutants occur in flue gas in two phases: particulate phase and gas phase consisting of semivola-tile and volatile compounds with boiling points higher than 100ºC. The project was dedicated to gas phase volatile compounds. Their concentrations were deter-mined by an off-line method. The sample probe was made from stainless steel and was fitted with heated gas filters. Two ceramic coaxial filters were used for the

removal of particulate substance from a sample gas. After filtration, the sample gas was transported through a heated stainless steel tube to a dry-ice-cooled conden-sate trap (to separate a condensate) and to a gas adsorp-tion tubes (two tubes of XAD-2 resin and one tube of activated carbon). Gas filters and gas transported line were kept at the same temperature of 180ºC to avoid condensation. In each run, the sampling flow rate was of 1l/min and the gas volume sample was about 300 liters. After completion of the sampling the con-densate trap and sorbent tubes were hermetically clo-sed, wrapped in aluminium foil and shipped to the labo-ratory in a portable refrigerator. Samples were analyzed in the following 48h (to prevent degradation) using a GC/MS system, manufactured by Shimadzu (Japan).

Very low concentrations of SO2 (in the range 20-35 ppmv) and NOx (in the range 15-25 ppmv) occurred in the flue gas. Table 2 presents the VOCs identified in the light oil combustion gases.

Table 2. VOCs identified in the light oil combustion gases.

Compounds group

Subgroup Concentration [µg/Nm3]

Aliphatic hydrocarbons

Alkanes Alkenes

101

101 Aromatic hydrocarbons PAH Oxidized aromatic

BTX 2- and 3-ringed Aromatic acids Aromatic alde-hydes

101-102

101-102

101-102

101-102

Hydrocarbons

Hydrocarbons contain-ing sulphur

Aromatic alcohols

Thiophenes Thiazoles

101-102

100

100

The identified volatile organic compound occurred in low concentrations of µg/Nm3. Among them in the higher concentrations of 10-100 µg/Nm3 were detected: aromatic hydrocarbons, oxidized aromatic hydrocar-bons and 2- and 3-ring PAHs. The main adverse envi-ronmental impacts of VOCs are connected with the photochemical ozone formation in the atmosphere. In the case of this flue gases these effects were insignifi-cant due to the low identified concentration of NOx which is necessary for these photochemical reactions. The 2- and 3- ring PAHs do not reveal the carcinogenic effect on humans. Thus the total environmental reactiv-ity of this flue gas is very low.

References [1] A. G. Chmielewski et al., IAEA-SM-325/124, Vienna

(1992)

ANNUAL REPORT 2007 Radioisotope Centre POLATOM

95

RADIOISOTOPE CENTRE POLATOM K. Małetka, A. Markiewicz, R. Mikołajczak, E. Byszewska-Szpocińska, T. Dziel


Radioisotope Centre POLATOM, since January 1st 2007 in the structure of the Institute of Atomic En-ergy, is active in the research and development of appli-cation of radioactive isotopes in science, nuclear medi-cine, industry and environmental protection.

The main Research and Development domains of Ra-dioisotope Centre are: - new radiopharmaceuticals showing the affinity to

cell receptors for diagnostic purposes and for radio-immunotherapy;

- radiopharmaceuticals containing peptides, proteins and monoclonal antibodies for imaging of inflam-matory sites;

- methods of elements separation and their applica-tion for production of radionuclides of high specific activity, including radionuclides generators;

- new types of miniature sealed sources for brachytherapy;

- new types of sealed radiation sources for industrial applications;

- development of preparation methods for manufac-turing radiopharmaceuticals, radiochemicals and medical materials;

- studies on the analytical techniques for quality assurance of medical products;

- development of methods for radiation activity measurement and determination of radionuclides in radioactive materials;

- new reference materials for ionizing radiation measurement.

Since 1999 RC POLATOM has been depositary of national standard unit of radionuclide activity to which the parameters of other reference materials are related through a chain of comparisons. The national standard is supervised by the President of The Central Office of Measures (GUM).

In 2007 several issues have been successfully accomplished:

- development of technology and implementation of isotope generator 188W/188Re production;

- manufacturing technologies for carrier free 90Y and carrier-added 177Lu suitable for labeling of radiopharmaceuticals for therapeutic use;

- manufacturing methods of 123I-α-methyl-tyrosine and 131I-α-methylotyrosine for diagnosis of brain tumour and its metastasis;

- method of internal electrolysis used for deposition of 106Ru and 125I layers on metallic surface for manufacture of active cores of sealed sources;

- manufacturing technology of 125I sealed sources in the form of miniature 125I seeds for brachytherapy of intrabrain, prostate and eyeball tumours;

- development of technologies for manufacture of peptide based kits for 99mTc-labelling for use in on-cological diagnostics;

- development of absolute measurement methods of radionuclides’ activity with liquid scintillation counters (LSC).

The Centre has developed very good communica-tion links with the leading clinical centers and nuclear medicine departments and Institutes in Poland involved in radiopharmaceutical and radiobiological develop-ments as well as with many international research insti-tutions. This cooperation is supported by scientific and applied grants provided by Ministry of Education and Science. The Centre actively contributes to the research projects carried out by the international organizations and programs: - International Atomic Energy Agency (IAEA); - European cooperation program in the field of scien-

tific and technical research COST; - EUREKA Initiative.

Since 2005 RC POLATOM is a member of Con-sortium and takes part in the Network of Excellence Diagnostic Molecular Imaging (DiMI), in the frame-work of sixth program, FP6 of the European Commu-nity.

Radioisotope Centre POLATOM ANNUAL REPORT 2007

96

ELECTROCHEMICAL PROCESSES OF FIXING RADIONUCLIDES APPLIED

IN SEALED SOURCES FOR BRACHYTHERAPY I. Cieszykowska, M. Mielcarski


One of the methods frequently used in oncology is radiotherapy. In particular, dynamic development of brachytherapy is observed recently [1]. In this treatment sealed radiation sources of 106Ru, 125I and in some cases also 192Ir, 90Sr or 103Pd are used. The most important task for manufacturing such sources is fixing of the radionuclides to the source cores [2-4].

Our results on application of electrochemical meth-ods, in particular of the internal electrolysis [5], to the source fabrication are presented in [6]. These methods appeared to be effective for fixing both metallic (106Ru, palladium) and non-metallic (125I) deposits as well as 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-tained were 2 µm thick, metallic and lustrous, adhering well to the silver backing, showing no tendency to chip-ping or cracking.

The high quality of the deposit obtained with a car-rier-free 125I reduced contamination problems and made this choice more reasonable from a practical point of view. As a result of the process lasting 70-90 h, 97-98% of 125I contained in the electrolyte solution was with-drawn.

For each technique applied, the yield and the uni-formity of deposition as well as the leachability were determined. The leachability of 125I fixed to the unpro-tected silver bars does not exceed 0.1% and is even lower for protected bars (Table 1).

Nevertheless, in the case of an unprotected source the leachability was still lower than others’ results [7].

Table 1. The leachability of 125I wire sources.

Description of source

Activity of source [MBq]

Activity leached out [kBq]/[%]

Protected Ag wire

35.43* 15.3*/0.04

Unprotected Ag wire

40.00* 43.1*/0.1

* Uncertainty of activity determination ± 5%

The distribution of 125I along the wire is fairly good. However, a wide maximum is observed for the central part of the wire (Fig. 1).

Fig. 1. Activity distribution along the unprotected silver wire.

The developed methods of fixing of 106Ru and 125I on a silver base enabled manufacturing of ophthal-mic applicators with a monolitic active core of the activ-ity required for therapeutic applications (13-27 MBq for 106Ru and 1.85-9.25 GBq for 125I).

References [1] J. Sienkiewicz et al., Wiad. Lek., 55 569 (2002) [2] C. Mathew et al., App. Radiat. Isot. 57 359(2002) [3] Ch. Zhang et al., App. Radiat. Isot. 57 309 (2002) [4] R. Monolkar et al., App. Radiat. Isot. 59 145 (2003) [5] G. Milazzo, Electrochemistry, Elsevier, Amsterdam

(1963) [6] I. Cieszykowska. PhD Diss., Institute of Nuclear Chem-

istry and Technology, Warsaw (2007) [7] R. Kuznetsovert et al., IAEA-TECDOC-1512 (2006)


97

THE DEVELOPMENT OF A PREPARATION METHOD OF ALBUMIN MICROSPHERES AS POTENTIAL RADIONUCLIDE

CARRIERS FOR DIAGNOSTIC AND THERAPEUTIC USE J. Pijarowska, A. Jaroń, E. Iller


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-tion method of batches of albumin microspheres with reproducible statistics, reproducible physical and bio-logical parameters which can be labeled with a variety of radionuclides and will comply with the requirements for API (Active Pharmaceuticals Ingredient). In general, the preparation of HAM consists in dispersion of a hu-man serum albumin (HSA) solution in a suitable me-dium and heat stabilization of spherical particles.

In the present study HAM were prepared by the emulsification and heat stabilization technique de-scribed previously [3,4], with minor modifications. The processing parameters of homogenization (speed and time), oil phase (volume, emulsifier and denaturating factor concentration), water phase (volume and HSA concentration) and protein denaturation heat (temperature and time) were selected in an experimental way. The optimized method consisted of adding a HSA solution containing SDS to liquid paraffin containing SDS and Tween 80 and stirring the mixture with me-chanical stirrer to obtain water/oil emulsion. This emul-sion was then heated to allow the formation and solidi-fication of microspheres. The supernatant oil was re-moved by decantation and microspheres were washed with diethyl ether. Then particles were dried in vacuum and later sieved.

Ten batches of microspheres ranging in a diameter from 10 to 32 µm were prepared by the described method. The particle size analysis was performed by an optical microscopy using a light microscope equipped with an ocular micrometer and a light camera (Fig. 1).

The microspheres were sized and photographed in a normal saline containing Tween 80 to prevent aggregation. The particles in each prepared batch were measured using a calibrated ocular micrometer and a special computer program.

Fig.1. Optical micrographs of HAM in average size range of 10-32 µm taken at two different magnifications (×200 and ×400).

The percentage frequency of microspheres particles in particular the size range was determined by weight analysis (Table 1).

Table 1. Particle size ranges of albumin microspheres.

Frequency of HAM[%] Size range [µm]

Batch No.

<10 10-32 32-50 50-100 >100

1 0.9 86.9 7.2 2.3 2.7 2 0.4 84.1 11.8 2.2 1.5 3 0.3 81.8 13.9 2.1 1.9

Average 0.5 84.3 11.0 2.2 2.0

The average production yield of the desired HAM size range of 10-32 µm amounts to 84% and the mean size of particles was approximately 15 µm. Optical micrographs show microspheres as very regular spheri-cal forms with quite smooth surfaces and slight scatter of size in the dominant range (Fig. 1).

In continuation of this project the albumin microspheres will be labeled with 99mTc and β-emitter radionuclides. For the HAM labeling with 99mTc the reduction of technetium valency is necessary. As reduc-tor SnCl2×2H2O will be used and the development of a method of attaching technetium to microspheres will be required. The prepared radiopharmaceuticals will be then tested for their in vivo stability and biodistribution.

References [1] B.A. Rhodes et al., Radiology 92 1453 (1969) [2] G. Wunderlich et al., Appl. Radiat. Isot., 52 63 (2000) [3] R.L. Evans, US Patent Office 663.687, (16.05.1972) [4] B. Łucka et al., Report 174/OpiDI (1981)


98

NEW DIAGNOSTIC KIT HYNIC-IGG LABELLED WITH TECHNETIUM-99 m 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-tion enables the determination of both location and number of infectious and inflammatory foci throughout the body. Since scintigraphic images are based on func-tional tissue changes, infectious and inflammatory foci can be visualized in their early phases, when anatomical changes are not yet apparent. IgG accumulates in infec-tious foci by a non specific extravasation due the locally enhanced vascular permeability. The 99mTc – labelled preparations have known ideal radiation characteristics. Gammaglobulin can be labelled by a direct or indirect method of radiotracer incorporation in the protein mole-cule. The direct method of labelling is connected with changes in the secondary and tertiary structure of IgG molecule. The indirect labelling method using bifunc-tional chelate hydrazinonicotinamide (HYNIC) pre-serves the structure and biological activity of the protein [1-3].

The HYNIC-IgG conjugate with a HYNIC:IgG 2:1 molar ratio lyophilized in citrate buffer pH 5.5 stable in 4-8º C for 6 month was obtained. The method of techne-tium-99m labeling of this conjugate was investigated in the presence of SnCl2 as a reductor and tricine as a coli-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 µl, citrate buffer pH 5,5; vial II – 11.7 µg SnCl2×2H2O) + 200 µg tricine in 200 µl 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 37ºC.

In the animal biodistribution studies, 24 h post in-jection (p.i) of 99mTc-HYNIC-IgG a high specific radio-activity accumulation in the inflamed thigh muscle compared with a non treated muscle was observed (Fig. 1).

0

0.5

1

1.5

2

2.5

liver kidney nontreatedmuscle

inflammedmuscle

organ

% ID

/g o

rgan

3 h24 h

Fig. 1. The time- dependant organ biodistribution of 99mTc-HYNIC-IgG in rat with an inflamed thigh muscle after 3 and 24 h p.i.(% administration dose per gram of an organ).

Scintigraphy with 99mTc-HYNIC-IgG was perfor-med in patients with clinically osteomielitis or septic arthritis. The relative uptake of the radiopharmaceutical in inflammation spots comparing to the background was very high (Fig. 2).

Fig. 2. SPECT/CT scintigraphy with 99mTc-HYNIC-IgG, ac-quisition 24 h after the tracer administration indicating an inflammatory process in the right hip.

The obtained new human immunoglobulin deriva-tive IgG-HYNIC labelled with 99mTc by the indirect method with a high radiochemical purity can be very 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)


99

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-tial for nuclear medicine, which belongs to the beta –gamma emitters group (maximal energy of beta radia-tion is 2.11 MeV, energy of gamma rays is 155 keV). With beta particles penetration in soft tissues of about 8 mm the cancer tissues can be destroyed, while the emission of gamma radiation permits imaging to locate accumulation. Studies include the clinical use of 188Re complexes with HEDP as an effective pain palliation agent in painful bone metastases and with DMSA for cancer treatment. 188Re complexes with peptides and monoclonal antibodies and their use in therapy against cancer are also in progress. Sterile and pyrogen-free solutions of 188Re agents have been used in brachyther-apy of coronary vessels to prevent restenosis [1-5].

Because of the short half-life of 188Re, supplying the medicament to remote customers can create a logis-tic problem, which can be solved by delivering 188W/188Re generators as a source of 188Re [6,7]. We have used a generator column and lead shielding used in our standard 99Mo/99mTc generator (fission produced 99Mo) to fabricate 188W/188Re generators. Aluminium oxide (Alumina A, ICN, MP Biomedicals) was used as a solid support. Before loading 188W, the support was activated by subsequent washing with the following solutions: 5 ml 0,9% NaCl solution acidified to pH=3, 5 ml 32% HCl and 20 ml 0,9% NaCl solution, pH=3, all at a flow-rate 10 ml/min, to obtain an effluent of pH=3.

The 188W (RIAR, Russia) with a specific activity between 27 GBq/g W and 133 GBq/g W, was dissolved, before loading on the column, in 0.5M NaOCl (0.5 ml NaOCl per 1 g of W), 80% CH3COOH (1 ml CH3COOH per 1 g of W) and 32% HCl, in order to lower the pH of the solution to 2.5, to obtain tungstenic acid. The 188W solution (as H2

188WO4) was then slowly loaded on the column using a peristaltic pump (flow rate 0.1 ml/min). The chemical quantity of W loaded on the column was between 40 to 80 mg/g of alumina. The 188Re was eluted from the generator with 0.9% acidified saline.

The elution profile of the generator is presented in Fig. 1 where average values of generator yields obtained in 10 consecutive elutions (over the period of 4 weeks) are shown. More than 95% of 188Re activity were accu-mulated at first and second fractions. The 188W/188Re equilibrium is reached in about 72 hrs, however, 188Re 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,

because the 188W mother radionuclide has the half-life of 69 days.

In our testing procedure the performance of the generator has been evaluated for 6 months period. Ac-cording to this procedure several generators were fabri-cated with a nominal activity of 188Re in the range from 4 to 15 GBq at the calibration date. The activities of the 188Re obtained from a generator were up to 500 mCi at the calibration date and over 90% of activity was eluted in first 4 ml of effluent (radioactive concentration of 188Re from 15 to 120 mCi/ml), hence no post-elution concentrating was needed. The radiochemical purity was above 98.0% and radionuclidic purity >99.9% with respect to gamma impurities. 188W leakage was <0.5%, whereas chemical purity testing showed Al < 10 ppm. The eluates were sterile and free of bacterial endotoxi-nes. The quality of the 188Re solution has been tested in labelling of bombesin analogue [8]. Described genera-tors can be used in the clinics for routine applications as well as in research laboratories.

0%

20%

40%

60%

80%

100%

1 2 3 4

Number of fraction

Rel

ativ

e yi

eld

Fig. 1. The yields of 188Re elution in collected 4 ml fractions over 10 consecutive elutions .

We acknowledge the support of the IAEA coordinated research project No 12880. References [1] K. Liepe et al., Am J Hosp Palliat Car. 22 457 (2005) [2] S. Lee et al., Am Heart J. 158 (2006) [3] B. Lambert et al., Eur J Nucl Med Mol Imaging. 33 344

(2006) [4] S. J.Wang et al., Nucl Med Biol. 28 727 (2001) [5] G. Ferro-Flores et al., Nucl Med Biol. 26 57 (1999) [6] F .F. Knapp et al., Anticancer Res. 17 1783 (1997) [7] F. F. Knapp et al., Anticancer Res. 17 1803 (1997) [8] E.Koumarianou et al., J Label Compd Radiopharm. 50

S241 (2007)


100

THE INTERCOMPARISON OF 99mTc AND 131I MEASUREMENTS BY RADIONUCLIDES CALIBRATORS IN POLISH HOSPITALS 20 07

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-eign metrological laboratories [1, 2], the Laboratory of Radioactivity Standards (LRS) has organized in Polish hospitals an intercomparison of activity measurements of 99mTc and 131I. Both radionuclides are generally used for diagnostics and therapy. Organization of the inter-comparison has been financed in 2007 by the National Atomic Energy Agency and supported by the Polish Society of Nuclear Medicine.

From among 58 Polish hospitals invited, 37 have participated in the intercomparison. Each hospital was identified by a confidential participant number.

The goal of the intercomparison was to obtain an information on the accuracy of activity measurements in Polish hospitals in relation to the National Standard Unit of Radionuclide Activity and to increase the efficacy of diagnostics, therapy and security of patients. All radio-active sources for measurements were manufactured in the RC POLATOM and delivered to participants suc-cessively during 4 months.

Each participant received about 4 ml of 99mTc elu-ate in a glass vacuum-vial used for elution, and two 131I capsules, low- and high-active, in separate glass vials. Sources were standardized in relation to the National Standard using a measurement system with the 4π ioni-zation chamber. The extended uncertainty of σLRS = ±1.5 % for 131I and of σLRS = ±3.0 % for 99mTc with the extension parameter k = 2 has been evaluated. An exact measurement time has been noted. Participants perfor-med measurements by their own radionuclide calibra-tors and sent results to the LRS. Data obtained from 37 hospitals participating in the intercomparison have shown a big variety of radionuclide calibrators used - 43 calibrators of 22 types from 12 various manufacturers.

The result given by each participant (Aparticipant) and the result obtained in the LRS (ALRS) was recalculated for the same reference date and the ratio

S = Aparticipant / ALRS

was determined. The half-life of (6.0067±0.0010) h of 99mTc and of (8.0233±0.0019) d of 131I was adopted [3].

Not all of participants have delivered an estimated uncertainty of measurement, and then it was impossible to evaluate their measurement results using the En crite-rion [4]. The statistical criterion called normalized stan-dard deviation, D

3LRS

LRStparticipan

σAA

D−

=

has been used. The ALRS was adopted as the reference value. The parameter D was used to classify the meas-urement results according to the specified limits [5]:

|D| ≤ 2 - good (within all limits), 2 < |D| < 3 - acceptable (within the warning limits), 3 ≤ |D| - non-acceptable (out of control).

The measurement result which differ no more than ±5% from the reference ALRS value was assumed to be suitable for hospitals purposes [6]. Then σLRS = 0.044·ALRS was adopted instead of σLRS values given above and, as a consequence, the warning limits of ±7.6% for acceptable results were obtained.

Good and acceptable results composed jointly of 75%, 69.2% and 82% for all measurement results in the case of 99mTc eluate, 131I capsules for diagnostics and 131I capsules for therapy, respectively (Table. 1). From 118 results received from participants, 23 (19.5%) were non-acceptable.

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 results

D ≤ -3

S ≤ 0.924

Acceptable results -3 < D < -2 0.924 < S < 0,95

Good results

-2 ≤ D ≤ 2

0.95 ≤ S ≤ 1.05

Acceptable results 2 < D < 3 1.05 < S < 1.076

Non-acceptable results

3 ≤ D

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 [1] D. MacMahon, et al., NPL Report DQL-RN 018, United

Kingdom (2006) [2] A. Iwahara, et al., Appl. Radiat. Isot. 56, 361 (2002) [3] Table de Radionucleides, BNM – LNHB/CEA, France

(2004)

[4] ISO/IEC Guide 43-1 (1997) [5] N. G. Natrella, Experimental statistics, NBS Handbook

91 3 (1963) [6] R. Gadd, et al., 93 NPL (2006)


101

ON PHOTON STATISTICS IN THE LS-COUNTER R. Broda


The method of radionuclide standardization by the TDCR technique is based on the statistical Poisson 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 be result of an optical phenomena occurring when the scintillation light is emitted from a LS-vial. Cassette and Vatin [4] have pointed out that the probability of photon emission from the LS-vial depends on the emission location and that the global statistics of light emission has a larger variance than the Poisson law.

Probabilities of successive elementary processes leading to the fluorescence of a liquid scintillator (ioni-zation along the particle track, quenching of primary 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 S1 states, energy transfer to the solute, fluorescence, internal conversion or quenching in the solute) were described using existing data [5 - 12].

The low-energy emitters 3H or 55Fe of an average energy of interacting particles of 5.7 keV, transfer about 10% of the energy to the π-electrons and create about 20 photons per disintegration in fine. Using the evaluated number of photons and the light emission efficiency, ε, versus the radius, R, of the emission point in a vial [4], the global distribution of light collection by pho-tomultipliers of a TDCR detector could be evaluated and compared with the Polya distribution. To simplify the calculations, only three binomial distributions for the number of photons, n, collected by photomultipliers were used. Distributions were calculated for three cylin-drical layers of scintillator of radius a) R ≤ 0.6, b) 0.6 < R ≤ 0.8 and c) 0.8 < R ≤ 1.0, and summed with the layer volume weighting factor u = 0.36, 0.28 and 0.36, re-spectively. The sum-distribution, which approximated global distribution of light collection, the binomial, the Poisson and the Polya distribution were calculated for the expected number n ≈ 2.6 of collected photons. The Polya distribution fits the global distribution of photons

quite well (Fig. 1), thus justifying its use for estimating the efficiency of low energy emitters..

Fig. 1. Approximation of the global distribution for the num-ber of photons, n, collected by photomultipliers from a LS-vial (dashed line) obtained by summing of the three binomial distribution a), b) and c) related to the differ-ent layers of scintillator.

The energy conversion factor for the liquid scintil-lator obtained when determining the 55Fe activity using the Polya model [3], enabled an estimation of the scintillation efficiency for 14C close to the experimental value. This gave further evidence of the correctness of the Polya model in the case of the 55Fe measurement.

References [1] R. Broda et al., Appl. Radiat. Isot., 39 (2) 159 (1988) [2] R. Broda, K. Pochwalski, in: J. E. Noakes, F. Schö

hofer, H. A. Polach, (Eds.), Liquid Scintillation Spec-trometry 1992, RADIOCARBON, The University of Arizona, Tucson, AZ, 255 (1993)

[3] R. Broda, A. Jęczmieniowski, Appl. Radiat. Isot., 60 453 (2004)

[4] P. Cassette, R. Vatin, Nucl. Instr. Meth. Phys. Res. A312 95 (1992)

[5] R. Cooper, J. K. Thomas, J. Chem. Phys. 48 (11), 5097 (1968)

[6] I. B. Berlman, J. Chem. Phys. 33 (2) 598 (1961) [7] J. B. Birks, in: D. L. Horrocks, C. T. Peng, (Ed.), Orga-

nic scintillators and liquid scintillation counting, Acad. Press, New York, (1971)

[8] J. B. Birks, The theory and practice of scintillation counting, Pergamon Press Ltd., Oxford, (1964)

[9] D. L. Horrocks, J. Chem. Phys. 52 1566 (1970) [10] D. L. Horrocks, Applications of liquid scintillation

counting, Acad. Press, New York, (1974) [11] C. W. Lawson, F. Hirayama, S. Lipsky, J. Chem. Phys.

51, 1590 (1969) [12] A. Weinreb, in: D. L. Horrocks, C. T. Peng, (Ed.),

Organic scintillators and liquid scintillation counting. Acad. Press, New York (1971)


102

SYNTHESIS AND TESTING OF GEL METAL-OXIDE COMPOSITES AS FILLING MATERIALS

FOR W-188/Re-188 GENERATOR COLUMNS E. Iller 1, H. Polkowska-Motrenko2, D. Wawszczak2, M. Konior 1

1Institute of Atomic Energy 2Institute of Nuclear Chemistry and Technology, Warsaw, Poland

Rhenium has recently showed up as a useful radio-isotope in variety of clinical trials.

At present the carrier–free Re-188 is obtained from W-188/Re-188 generators in which the tungsten-188 in form of a sodium tungstenate W-188 solution is ad-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 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-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 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-mination of their structures and chemical purity.

The neutron activation analysis and spectrometry were applied for the determination of radionuclidic purity of components

The X-ray diffraction analysis and the neutron scat-tering analysis (wide and small angles) allowed for a determination of their crystal structure [4].

The samples were analyzed by XRD using a Ri-gaku Miniflex diffractometer with Cu-Kα radiation (tube voltage 30kV and tube current 15mA) and scan-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-nation process by the Sonnevelt method and a Kα2 elimination process.

Next the elution profile of generator column packed on gels samples activated in a nuclear reactor have been studied using 0,9% NaCl solution as an elu-ent. The best results of elution (profile and eluent pu-rity) appeared in the case of filling a chromatographic column with WO3-ZrO2 materials; in which the oxides molar ratio was 1:2 and a calcination temperature of 500oC and WO3-TiO2 with molecular ratio 1:2 and a calcination temperature of 650oC. The structural analysis of both composites allowed for theirs classification as amorphous materials.

Samples containing WO3-ZrO2-SiO2 did not reveal satisfactory elution profiles.

10 20 30 40 50 60 70 80 90

10 20 30 40 50 60 70 80 90

T=500°C

Inte

nsity

2θ°

T=500°C (sample SP)

***

T=650°C

° ° ° *° ***

* °°°°

°°

°°

*

°T=800°C

(o) Monoclinic WO3 [71-2141]

(∗)

WO3 : ZrO2 = 1 : 2

Tetragonal ZrO2 [88-1007]

Inte

nsity

2θ°

Fig. 1. The X-ray diffraction analysis of WO3- ZrO2 (1:2) nanocomposites after different temperature treatment.

The work was supported by the research grant No 3 TO9B 042 29 of the Polish Ministry of Science and Education

References [1] M.S. Dadachov et al., Applied Radiation and Isotope

57 641 (2002) [2] M.S. Dadachov, R.M.Lambrecht, J. Radioanal. Nucl.

Chem. Letters 200 211 (1995) [3] M.S. Dadachov et al., J. Radioanal. Nucl. Chem. Letters

188 267 (1994) [4] J.J. Milczarek et al,. IAE Report 38-B (2007)


103

DEVELOPMENT OF RADIONUCLIDES STANDARDIZATION METHODS BY MEANS OF A LIQUID SCINTILLATORS TECHNIQU E

USING MONTE CARLO CALCULATIONS T. Dziel, R. Broda


The probabilities of interaction of photons in two different liquid scintillators (toluene and widely used commercial cocktail Ultima Gold) were calculated as a function of energy for two different geometries (stan-dard 20 ml LS glass vial and LS cocktail volumes of 10 and 15 ml) using the Monte Carlo code PENELOPE [1].

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. 1. Geometry of LS vial used in the Monte Carlo calcula-tions. All dimensions are given in cm.

The main calculations were performed over the photon energy range 5 – 1000 keV. For each energy value and geometry at least 2·106 initial particles were simulated and the radiation source was assumed to be uniformly distributed throughout the LS cocktail. The calculated probabilities of photon interaction for differ-ent liquid scintillators are comparable (Fig. 2).

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 [1] F. Salvat et al., PENELOPE-2006 Workshop Proce-

edings, Barcelona, Spain, 4-7 July (2006) [2] P. Casette et al., Appl. Rad. Isot. 64 1471 (2006)

ANNUAL REPORT 2007 Publications, Conferences, Seminars, Workshops, Research projects, Education

107

PUBLICATIONS

ARTICLES

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).

Publications, Conferences, Seminars, Workshops, Research projects, Education ANNUAL REPORT 2007

108

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 99mTc-EDDA/HYNIC-Tyr3-octreotide and 99mTc-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).


109

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).


110

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.


111

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., Garboli ński 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.


112

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., M ądry 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.

127. Szyszko T., Prokocki P.: Master Plan of validation of the 90Sr (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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130. Szyszko v. ChorąŜy T.: Validation documents for 90Sr(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.


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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.


119

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.


120

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., Wojdowsk a 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).


121

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).


122

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 LaSr3Fe3O10 in temperature range 25-650 oC. American Institute of Physics Conf. Proc., 633, 2007.


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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.


124

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.


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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).


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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


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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


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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 - L. Fuks, M. Neves (IChTJ and ITN): Towards complexes with the [99mTc(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., M ądry 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.


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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.


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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


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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 PROJ ECT

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


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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.


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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


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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)


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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


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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.


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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


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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


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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 Balzarini J. 67 Banaszak J. 61 Bielewicz M. 36 Boimski B. 31 Borysiewicz M. 80, 81, 82, 83, 84, 85, 89, 90 Borysiewicz M. A. 90

Broda R. 100, 101, 103 Byszewska-Szpocińska E. 95, 98 Chmielewski A. G. 91 Chojnowski M. 60 Chwaszczewski S. 40 Cieszykowska I. 96 Czachor A. 49, 50, 53 Czarnocki Z. 66 Czerski Ł. 82, 85, 90 Czerski P. 40 De Cargouet G. 35 Didyk A.Yu. 71, 72 Droździel A. 74, 75 Duda P. 42, 43 Dyczewski J. 82, 85, 90 Dziel T. 95, 100, 103 Dzikowski W. 42 Fijał-Kirejczyk I. 59, 60, 61, 62 Filipiak B. 23 Galmarini S. 87, 88

Garanty I. 82, 84, 85 Golnik N. 23, 26, 27, 28, 30 Gołąb A. 15 Górska-Chrząstek M. 98 Górski L. 70 Graeff W. 54, 55, 56, 57, 58 Gronkowski J. 55 Gryziński M.A. 26, 29 Guzdek P. 63, 64 Haratym Z. 23 Iller E. 62, 97, 102 Jankowska-Kisielińska J. 49, 59 Jaroń A. 97 Jaroszewicz J. 15 Jaworska K. 45 Jędrzejec H. 82 Józefowicz E. T. 23 Józefowicz K. 23, 31 Jurkowski Z. 60, 61, 62

Kacprzyk W. 81 Kapuściński J. 98 Karczmarczyk U. 98 Kilim S. 35, 36 Klisińska M. 39 Kołakowska E. 100 Kołodziejak K. 56 Konior M. 99, 102

Kowalczyk G. 60 Kowalski G. 55 Kozubal A. 82, 84, 85 Krukowski A. 66 Krzysztoszek G. 15 Kulikowska T. 20 Kuśmierek J. 98 Lefeld-Sosnowska M. 54, 57 Licki J. 91 Listkowska A. 100 Łukasiewicz T. 56, 57 Łuszcz M. 40 Malinowska A. 54, 57 Malinowski M. 56 Małetka K. 95 Marcinkowska Z. 20 Markiewicz A. 95 Maurin J. K. 66, 67 Mączka D. 74, 75 Michalik J. 98 Mielcarski M. 96 Mikke K. 59 Mikołajczak R. 95, 99 Milczarek J. J. 49, 50, 58, 60, 61, 62 Muklanowicz A. 100 Orzeszko A. 67 Orzeszko B. 67 Ostapczuk A. 91 Ośko J. 28 Paluchowska B. 68, 69 Parus J.L. 99 Patocka A. 100

Patrycy A. 45 Pawlak D. 99 Pawłowski A. 70 Pęczkowski P. 53 Pieńkowski Ł. 100 Pijarowska J. 97 Pliszczyński T. 23 Pochrybniak C. 58 Polkowska-Motrenko H. 102

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Potempski S. 81, 82, 85, 86, 87, 88 Pszczoła J. 63, 64 Pyszniak K. 74, 75 Saniewski G. 45 Semina V. 72 Sielanko J. 74, 75

Sikorski M. 43 Słowiński B. 41, 42, 43, 71 Słupiński T. 55 Snopek B. 23 Sobczak R. 41 Stoch A. 63, 64 Stoch P. 63, 64, 65 Strugalska-Gola E. 35, 36 Strupczewski A. 44, 45 Suwalski J. 63, 64, 65 Szczurek J. 40 Szteke W. 52 Szuta M. 35, 36, 37, 38

Tulik P. 31 Turek M. 74, 75 Wasiuk, A. 82, 85 Wawszczak D. 102 Wierzbicka E. 57, Wierzchowski W. 54, 55, 56, 57, 58 Wieteska K. 54, 55, 56, 57, 58 Wilczyńska T. 71, 72, 73 Wiśniewski R. 71, 72, 73 Wojciechowicz H. 82, 85, 90 Wojciechowski A. 35, 36, 38 Woźnicki Z. 35 Wójcik T. 63, 64, 65 Zachariasz P. 63, 64, 65 Zielczyński M. 26, 27, 30, 31 Zuchlińska M. 99 Żołądek Jan 60, 61, 62 Żołądek Joanna 60, 61, 62

institute of atomic energy

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