(2) AUSTRALIA

(3) AUSTRIA

Helmuth Böck.

Helmuth Böck is Professor for Reactor Safety at the Atominstitute of the Austrian Universities and Manager of the 250 kW TRIGA Mark II reactor operated for students training and education.

Graduated from the Technical University Vienna in 1966 with a Masters Degree in Physics and a PhD in 1979 in Nuclear Technology he is deeply involved in the training and education of Masters and PhD students in the fields of reactor safety, reactor instrumentation, probabilistic safety assessment, nuclear safeguards and related fields. At the Technical University Vienna he carries out practical courses in the fields of reactor kinetics and dynamics and on reactor instrumentation where the students work directly at the TRIGA reactor in groups of 3-4 students on practical experiments using the various reactor systems for their experiments. He further lectures on nuclear engineering and organises a seminar on reactor safety.

Since 1975 he has been technical expert to the IAEA in the fields of research reactor utilization, research reactor safety and reactor operators training and has carried out more than 50 expert missions to countries in Asia, Africa and South America. He further carries out regular training course for junior IAEA safeguards trainees and has trained more than 60 IAEA fellows under the IAEA fellowship programme at the Atominstitute.

In addition these courses are also carried out for staff members of nuclear facilities or nuclear organisations from neighbouring countries such as from Germany or the Slovak Republic. Recently he coordinated an ENEN (European Nuclear Engineering Network)-course between the Atominstitut and the Technical Universities of Budapest, Bratislava and Prague.

He has published more than 240 articles in scientific journals or at international scientific conferences. He is president of the Austrian Nuclear Society, member of the German Nuclear Society and Austrian representative in an EU commission on decommissioning and waste management of nuclear research centres.

Prof. DI. Dr. Helmuth Böck
Atominstitute of the Austrian Universities
Stadionalle 2
A-1020 Vienna
Tel: ++43 1 58801 14168
Fax: ++43 1 58801 14199
e-mail: boeck@ati.ac.at
www.ati.ac.at

(4) BELGIUM

William D'haeseleer.

William D. D'haeseleer is Full Professor in the College of Engineering of the University of Leuven (K.U.Leuven), Belgium.

(Note: K.U. Leuven - the "Katholieke Universiteit Leuven - was founded in 1425 and is the oldest and largest university of Belgium.)

Over the years, he has taught courses in Nuclear-Reactor Physics, Nuclear-Reactor Technology, Radiation Shielding, Safety Aspects in Nuclear Facilities, Energy Technology & Energy Economy, Thermal Systems & Energy Management, Applied Thermodynamics & Energy Engineering, and Renewable Energy,. His research activities are situated in the areas of Energy Conservation & Energy Management, Energy & Environment, Energy Systems, and Energy Policy. He is Director of the University of Leuven Energy Institute. He is also Division Head of the Division of Energy Conversion & Applied Mechanics and founder of the Energy Foundation Industry - University. In addition, he heads the K.U.Leuven Center of Nuclear Engineering, which since 2001 acts as the coordinating cell of the K.U.Leuven contribution in the Belgian Nuclear higher Education Network (BNEN), of which he is Vice-President. He is an active member of the European Nuclear Education Network (ENEN) where he acts as one of the architects of the model for a degree of European Master of Science in Nuclear Engineering.

William D'haeseleer obtained the degrees of University Graduated Electro-Mechanical Engineering (option Energy) and Nuclear Engineering from the K.U.Leuven in 1980 and 1982, respectively. In December 1983, he graduated as Master of Science in Electrical Engineering from the University of Wisconsin-Madison (UW-M), USA. He obtained his Doctoral Degree (PhD) at that same university UW-M in May 1988. From 1988 till 1993, he resided in Germany, where he was a Scientific Staff Member of the NET Team at the Max-Planck-Institut für Plasmaphysik in Garching-bei-München. From 1993 till 1996, he was active in the Belgian engineering branch of its major utility, Tractebel Engineering, where he was Manager of the Mechanical Design Section, and Research & Development Manager of the Nuclear Department. As of October 1996, he is a faculty member at the K.U.Leuven.

He has been a Fulbright Fellow, and in 1989, he has been Visiting Assistant Professor at the Rennselaer Polytechnic Institute in Troy, New York.

He was an active member of the Belgian AMPERE (Analysis of the Means for the Production of Electricity and Re-evaluation of the Energy Carriers) Commission, he was chairman of the European Commission's External Advisory Group on Thermonuclear Fusion (EAG-FU) and he is now member of its Advisory Group on Energy.

William D. D'haeseleer
University of Leuven Energy Institute
c/o Energy Conversion & Applied Mechanics
Celestijnenlaan 300A
B-3001 LEUVEN (Heverlee), Belgium
Tel: +32-16-32 25 11 or +32-16-32 27 79 (fixed office phones)
Tel: +32-475-35 67 66 (cellular phone)
Fax: +32-16-32 29 85
william.dhaeseleer@mech.kuleuven.ac.be
www.kuleuven.ac.be/ei
www.mech.kuleuven.ac.be/tme
www.sckcen.be/enen

(6) BULGARIA

(7) CANADA

(8) CHINA

(9) CZECH REPUBLIC

Karel Matejka.

Karel Matejka is Full Professor in the Faculty of Nuclear Sciences and Physical Engineering (FNSPE) of the Czech Technical University in Prague, Czech Republic.

He is head of the Department of Nuclear Reactors at FNSPE. Education: Czech Technical University, Prague, Faculty of Nuclear Sciences and Physical Engineering (FNSPE), M.Sc. in nuclear Engineering (1969), Ph.D. in Application Physics (1978), Prof. in Nuclear Engineering (1993). Specialisation: Nuclear reactor Physics and technology, experimental reactor physics, nuclear safety, operation in research nuclear installations.

More than thirty years of experience in experimental reactor physics, research nuclear installations, wide pedagogical activity at the University, quality assurance of software and hardware, experimental reactor operator authorisation, construction and operation of the VR 1 training reactor, preparation of the VR 1 educational system, publications for education.

He is experienced in several positions in the frame of the Faculty, where he is engaged in all his practices (specialist, scientific worker, chief of the VR 1 reactor), since 1991 he has been a head of the Department of Nuclear Reactor.
From the beginning he was oriented on experiments, later he was solving many tasks in the frame of a development of technology and science, he took part in construction studies of the training reactor VR 1 located in the Nuclear Engineering Faculty. Since 1975 he had been fully engaged in the construction of the VR 1 reactor. His effort was one of the main supports (computations, safety analyses, construction work, start up, operation) to start an operation of this reactor in 1990. He has managed activities to use the VR 1 reactor for education of students from several universities and workers of nuclear power installations.

His pedagogical activity covers supervision, consultation and assessment of many diploma work, exercises in several subjects, seminars, and special lectures. Since 1990 he has taught several subjects (experimental neutron physics, experimental reactor physics, a course of operators) at the Faculty and also he has taught students and other course participants to know and understand behaviour of the VR 1 reactor. He was engaged in preparation of syllabus of a new subject (nuclear energy and environment), nuclear installation BSc. study.

He co-operates mainly with the Nuclear Research Institute in Rež (NRI), State Office for Nuclear Safety, Nuclear Power Plant Dukovany, Nuclear Power Plant Temelín and educational centre of nuclear operators in Brno, many faculties of various universities (education on the VR 1 reactor) and many grammar and professional schools. He has had also very good contact with many institutions abroad. He is an author or he co-operated on more then 200 publications (original topics, textbooks, research reports, studies, design).

Karel Matejka
Czech Technical University in Prague
Faculty of Nuclear Sciences and Physical Engineering
Department of Nuclear Reactor
Tel: +420 284 681 075
Fax: +420 284 680 764
E-mail: matej@troja.fjfi.cvut.cz
www.fjfi.cvut.cz/DesktopDefault.aspx?ModuleId=1029
www.fjfi.cvut.cz/DesktopDefault.aspx?ModuleId=523

(10) FINLAND

Riitta Kyrki-Rajamäki.

Riitta Kyrki-Rajamäki (M.Sc.Tech. 1976 and Dr.Tech. 1995 in technical physics in Helsinki University of Technology) is professor of Nuclear Energy Technology in Lappeenranta University of Technology (LUT) at Department of Energy and Environmental Technology. Her research interests include safety, transient and accident analyses as well as experimental work on thermal hydraulics of nuclear power plants. Until 2002 she worked in the Technical Research Centre of Finland (VTT) as chief research scientist developing, validating and applying in-house three-dimensional reactor dynamics codes and methods on NPP licensing analyses (reactivity initiated accidents, anticipated transients without scram, inhomogeneous boron dilution).

Riitta Kyrki-Rajamäki
Lappeenranta University of Technology
Department of Energy and Environmental Technology
P.O. Box 20
FIN-53851 Lappeenranta
Finland
Tel: +358 5 621 2705
Tel: +358 400 508 948 (cellular phone)
Fax: +358 5 621 2799
E-mail: riitta.kyrki@lut.fi
WWW: www.lut.fi

(11) FRANCE

(12) GERMANY

(13) INDIA

R B Grover.

Dr R B Grover is concurrently holding the following positions:

• Director, Strategic Planning Group (SPG), Department of Atomic Energy (DAE),
  
• Associate Director, Technical Coordination & International Relations Group, Bhabha Atomic Research Centre (BARC).

As Director SPG, Dr Grover is coordinating the following activities:

• Formulation of strategic plans for the department.
• Energy planning and nuclear fuel cycle studies.
• Human resource development.
• Funding of extra-mural research.
• Public awareness programmes.
• International studies and relations.

At BARC, Dr Grover's group is engaged in the following activities:

• Library and information services.
• Human resource development.
• Technology transfer and collaborations at the national and international level.
• Management services and technical coordination.

In the recent past, he has been responsible for several initiatives in the fields of energy planning, technology transfer, human resource development, extra-mural funding, information services and the formulation of the X five-year plan for the department. He studied GDP growth and population growth scenarios for India and formulated a scenario for growth of electricity in the coming five decades. Considering the fuel resource position in the country, he formulated a strategy to meet the projected demand and the role to be played by nuclear power. This involved study of uranium resource position, reprocessing capability, concept to be chosen for fast reactors and fast reactor growth needed to meet the projected requirement for nuclear electricity.

Dr Grover has been with the Department of Atomic Energy for about three decades. During the first 25 years, he worked in the areas of reactor safety, fuel and core thermal-hydraulics and thermal design of heat exchange equipment. Dr. Grover is a Fellow of the Indian National Academy of Engineering and is a life member of the Indian Society of Heat and Mass Transfer and Indian Nuclear Society. He studied mechanical engineering at Delhi College of Engineering, Delhi and received Ph.D. from Indian Institute of Science, Bangalore.

(14) ISRAEL

(15) ITALY

(16) JAPAN

(17) KOREA

(18) MEXCIO

Carlos Chávez -Mercado

ACADEMIC RANK: Professor

DEPARTMENT AFFILIATION: Energy, National Autonomous University of Mexico (UNAM), College of Engineering.

He earned a Ph.D. degree in nuclear engineering from the Pennsylvania State University (1994) and a M.Sc. in Nuclear Science and B.Sc. in Chemistry degrees from the National Autonomous University of Mexico in 1985 and 1983 respectively.

Dr. Chávez-Mercado is a full professor of Nuclear Energy at the Engineering School of the National Autonomous University of Mexico. His current interests are in the areas of human-factors engineering, human-machine interface design, human-computer interaction and computer display system design applied to the safety of nuclear power plants.

Dr. Chávez-Mercado is the project leader for the design, development and installation of the Nuclear Reactor Engineering Analysis Laboratory which mainly includes the development of a classroom analysis simulator and advanced graphical analyzer of nuclear processes.

Research and Professional Experience:

DEGREES:

B.S., Chemistry, UNAM 1983
M.S., Nuclear Science, UNAM, 1986
Ph.D., Nuclear Engineering, The Pennsylvania State University 1994.

FIELDS OF SPECIALIZATION AND AREAS OF INTEREST:

Nuclear safety, human factors engineering, human reliability analysis, human-computer interaction and human-machine interface for process monitoring and control. Other areas of interest; dosimetry, analytical chemistry, mass spectrometry, and ion exchange separations methods. Strong knowledge in computer programming; C, FORTRAN, BASIC, LISP and ACSL. UNIX, LINUX and VMS operative systems.

SOME RESEARCH PUBLICATIONS:

• Salazar Cravioto J. H, Ramos Pablos J. C., Salazar Salazar Edgar, Chávez Mercado Carlos. "A RELAP/SCDAP Based Classroom Analysis Simulator for the Laguna Verde Nuclear Power Plant. Transactions of the American Nuclear Society. Vol. 88, pp 263-258.San Diego, California. June 2003.
• Chávez-Mercado, Carlos, Zayas Pérez, Benjamín, Ocampo-Mansilla, Héctor, Salazar-Salazar,Edgar, and Alanís-Cantú, Reynaldo. "Human Factors and the Nuclear Reactor Engineering Analysis Laboratory. Proceedings of the OECD/NEA Workshop Approaches for the Integration of Human Factors into the Upgrading and Refurbishment of Control Rooms, Halden, Norway, 23-25 August 1999.
• C. Chávez-Mercado, J. B. Morales-Sandoval, B. E. Zayas-Pérez. "NREAL: Nuclear Reactor Engineering Analysis Laboratory." Transactions of the American Nuclear Society, Vol.79, pp82-83. Washington, D.C., November 1998.
• C. Chávez-Mercado, B. Zayas-Pérez, J. Valdés-Parra, and H. Ocampo-Mansilla. "The Classroom Analysis Simulator: A Training and Research Tool for Nuclear Power Plant Operations." Proceedings of the 1997 IEEE 6^th Conference on Human Factors and Power Plants., Orlando, Florida.. Jun 1997
• C. Chávez Mercado, "An Advanced Graphical Human-Machine Interface for a Classroom Analysis Simulator of Nuclear Processes." Proceedings of the IERE Workshop on Human Factors in Nuclear Power Plants.Operation Session (2) Interface. TEPCO R & D Centers, Tokyo, Japan. May 1996.

RESPONSIBILITY IN THE PROGRAM:

Teaching/Research 100%
Fellowship Program Courses: Human Factors Engineering, Nuclear Reactor Safety, Chemistry.

OTHER PERTINENT DATA:

Responsible of the Nuclear Engineering Analysis Laboratory. Has been responsible of technical co-operation projects with the IAEA since 1997. Performed the Human Reliability Analysis for the Laguna Probabilistic Safety Analysis Level-II. Founder Member of the Mexican Nuclear Society since 1988, Member of the Human Factors and Ergonomics Society since 1990, IEEE Systems, Man, and Cybernetics Society since 1992. Mexican delegate and member of the Principal Working Group 1 on Operating Experience and Human Factors, OCDE/NEA form 1996 to 1999.

Juan-Luis François

ACADEMIC RANK: Professor

DEPARTMENT AFFILIATION: Energy, National Autonomous University of Mexico (UNAM), College of Engineering.

DEGREES:

B.S., Energy Engineer Metropolitan University of Mexico, 1979
M.S., Nuclear Engineering, National Institute of Nuclear Sciences and Techniques, France, 1984
Ph.D., Physical Sciences (Reactor Physics), University of Paris XI (Orsay), France, 1987

FIELDS OF SPECIALIZATION AND AREAS OF INTEREST:

Nuclear Reactor Design, Nuclear Fuel Management, Fuel Management Optimization, Advanced Fuel Cycle Design, Validation of Reactor Analysis, Codes and Benchmarks.

RECENT SIGNIFICANT RESEARCH PUBLICATIONS (5 YEARS):

• Núñez-Carrera, J.L. François, G. Espinosa-Paredes. "Comparison Between HELIOS Critical-Depletion Calculations and a PWR Thorium Cell Burnup Benchmark". Annals of Nuclear Energy, Vol 31/7 pp. 713-722, 2004.
• J.L. François, C. Martín del Campo, A. Tavares. "Development of a BWR Control Rod Pattern Design System Based on Fuzzy Logic and Knowledge". Annals of Nuclear Energy, Vol 31/4 pp. 343-356, 2004.
• Castillo, G. Alonso, L.B. Morales, C. Martín del Campo, J.L. Francois, E. del Valle. BWR Fuel Reloads Design Using a Tabu Search Technique. Annals of Nuclear Energy, Vol 31/2 pp. 151-161, 2004.
• J.L. Francois, C. Martin del Campo, R. François, L.B. Morales. A Practical Optimization Procedure for Radial BWR Fuel Lattice Design Using Tabu Search with a Multiobjective Function. Annals of Nuclear Energy, Vol 30/12 pp. 1213-1229, 2003.
• Martín del Campo, J. L. François, L. B. Morales. BWR Fuel Assembly Axial Design Optimization Using Tabu Search. Nuclear Science And Engineering 142, 107-115, 2002.
• J.L. Francois, C. Martin del Campo, J. Hernández. Design of an Overmoderated Fuel and a Full MOX Core for Plutonium Consumption in Boiling Water Reactors. Annals of Nuclear Energy, Vol 29/16, pp 1953-1965, 2002.
• Martín del Campo, J.L. François, H.A. López. AXIAL: A System for Boiling Water Reactor Fuel Assembly Axial Optimization Using Genetic Algorithms. Annals of Nuclear Energy, Vol 28/16, pp 1667-1682, 2001.
• J.L. François, J.L. Esquivel, C. Cortés, J. Esquivias, C. Martín del Campo. Validation of a Methodology for Fuel Management Analysis of Laguna Verde Nuclear Power Plant. Annals of Nuclear Energy, Vol. 28/5, pp 489-501, 2001.
• J.L. Francois, C. Martin del Campo, C.C. Cortes, E.Ramirez, J. Arellano. Development of an Automated System or Fuel Reload Patterns Design. Nuclear Engineering and Design, 193, 13-21, 1999.
• J.L. Francois, H.A. Lopez. SOPRAG: A System for Boiling Water Reactors Reload Pattern Optimization Using Genetic Algorithms. Annals of Nuclear Energy, Vol. 26/12, pp 1053-1063, 1999.

RESPONSIBILITY IN THE PROGRAM:

Teaching/Research 100%
Fellowship Program Courses: Fundamentals of Nuclear Engineering, Nuclear Reactor Analysis.

RECENT INDUSTRY EXPERIENCE OR CONSULTING WORK:

Mexican Federal Commission of Electricity, leader of several nuclear fuel management projects. EPRI project on "CPM-3 lattice code validation". IAEA cooperation project on "Development of Methodologies and Advanced Techniques Related to Nuclear Reactor Safety". Mexican Nuclear Regulatory Commission, project on fuel management and transient analysis.

OTHER PERTINENT DATA:

Member: ANS (American Nuclear Society), LAS/ANS (Latin-American Section of the ANS) SNM (Mexican Nuclear Society), AI (Mexican Academy of Engineering), SNI (Mexican National System of Researchers). President of the Mexican Nuclear Society, Member of the International Committee of the ANS, Member of the Program Committee of the ANS Reactor Physics Division, Member of the Executive Committee of the LAS/ANS, Member of the ANS Standard Committee for the Determination of Thermal Energy Deposition Rates in Nuclear Reactors (ANS-19.3.4), Member of Technical Programs of several ANS Reactor Physics and Mathematics and Computation Divisions' Meetings, Chaired numerous Technical Programs at National Meetings (Mexico), Editor of the Mexican Nuclear Society's Journal.

Cecilia Martín-del-Campo

ACADEMIC RANK: Professor

DEPARTMENT AFFILIATION: Energy, National Autonomous University of Mexico (UNAM), College of Engineering.

DEGREES:

B.S., Energy Engineer Metropolitan University of Mexico, 1979
M.S., Nuclear Engineering, National Institute of Nuclear Sciences and Techniques, France, 1984
Ph.D., Physical Sciences (Reactor Physics), University of Paris XI (Orsay), France, 1987

FIELDS OF SPECIALIZATION AND AREAS OF INTEREST:

Nuclear Fuel Management, Fuel Management Optimization, Advanced Fuel Cycle Design, Validation of Reactor Analysis, Codes and Benchmarks, Nuclear Energy and the Environment

RECENT SIGNIFICANT RESEARCH PUBLICATIONS (5 YEARS):

• J.L. François, C. Martín del Campo, A. Tavares. "Development of a BWR Control Rod Pattern Design System Based on Fuzzy Logic and Knowledge". Annals of Nuclear Energy, Vol 31/4 pp. 343-356, 2004.
• Castillo, G. Alonso, L.B. Morales, C. Martín del Campo, J.L. Francois, E. del Valle. BWR Fuel Reloads Design Using a Tabu Search Technique. Annals of Nuclear Energy, Vol 31/2 pp. 151-161, 2004.
• J.L. Francois, C. Martin del Campo, R. François, L.B. Morales. A Practical Optimization Procedure for Radial BWR Fuel Lattice Design Using Tabu Search with a Multiobjective Function. Annals of Nuclear Energy, Vol 30/12 pp. 1213-1229, 2003.
• Martín del Campo, J. L. François, L. B. Morales. BWR Fuel Assembly Axial Design Optimization Using Tabu Search. Nuclear Science And Engineering 142, 107-115, 2002.
• J.L. Francois, C. Martin del Campo, J. Hernández. Design of an Overmoderated Fuel and a Full MOX Core for Plutonium Consumption in Boiling Water Reactors. Annals of Nuclear Energy, Vol 29/16, pp 1953-1965, 2002.
• Martín del Campo, J.L. François, H.A. López. AXIAL: A System for Boiling Water Reactor Fuel Assembly Axial Optimization Using Genetic Algorithms. Annals of Nuclear Energy, Vol 28/16, pp 1667-1682, 2001.
• J.L. François, J.L. Esquivel, C. Cortés, J. Esquivias, C. Martín del Campo. Validation of a Methodology for Fuel Management Analysis of Laguna Verde Nuclear Power Plant. Annals of Nuclear Energy, Vol. 28/5, pp 489-501, 2001.
• J.L. Francois, C. Martin del Campo, C.C. Cortes, E.Ramirez, J. Arellano. Development of an Automated System or Fuel Reload Patterns Design. Nuclear Engineering and Design, 193, 13-21, 1999.

RESPONSIBILITY IN THE PROGRAM:

Teaching/Research 100%
Fellowship Program Courses: Nuclear Fuel Management, Energy and Environment.

RECENT INDUSTRY EXPERIENCE OR CONSULTING WORK:

Mexican Federal Commission of Electricity, contribution in several nuclear fuel management projects. Mexican Nuclear Regulatory Commission, project on fuel management and transient analysis. Participant at the IAEA Project: Comparative Assessment of Energy Sources for Mexican Electricity Supply until 2025 with DECADES and Comparative Assessment of Mexican Energy Options and Strategies until 2025 with ENPEP (Balance).

OTHER PERTINENT DATA:

Member: SNM (Mexican Nuclear Society), AI (Mexican Academy of Engineering), SNI (Mexican National System of Researchers), member of Technical Program at the International Joint Meeting of the LAS/ANS, SNM and SMSR in Cancun 2004, member of Technical Programs of several ANS Reactor Physics and Mathematics and Computation Divisions' Meetings, chaired several Technical Programs at National Meetings (Mexico).

Edgar Salazar-Salazar

ACADEMIC RANK: Professor

DEPARTMENT AFFILIATION: Energy, National Autonomous University of Mexico (UNAM), College of Engineering.

DEGREES:

B.S., Physical Sciences, Autonomous University of Nuevo León (UANL), 1982
M.S., Computation Sciences, Technological Institute and Superior Studies of Monterrey (ITESM), 1991

FIELDS OF SPECIALIZATION AND AREAS OF INTEREST:

Computer Based Training, Web Based Training, E-Learning. Other areas of interest; Computers Networks, Artificial Intelligence, Experts Systems.

SIGNIFICANT RESEARCH PUBLICATIONS :

• Salazar Cravioto J. H, Ramos Pablos J. C., Salazar Salazar Edgar, Chávez Mercado Carlos. "A RELAP/SCDAP Based Classroom Analysis Simulator for the Laguna Verde Nuclear Power Plant". Transactions of the American Nuclear Society. Vol. 88, pp 263-258.San Diego, California. June 2003.
• Chávez-Mercado, Carlos, Zayas Pérez, Benjamín, Ocampo-Mansilla, Hector, Salazar-Salazar, Edgar, and Alanís-Cantú, Reynaldo. "Human Factors and the Nuclear Reactor Engineering Analysis Laboratory. Proceedings of the OECD/NEA Workshop Approaches for the Integration of Human Factors into the Upgrading and Refurbishment of Control Rooms, Halden, Norway, 23-25 August 1999.
• E. Salazar, J. Arellano, M. de Loera, et. al.;"Sistema Experto para el Seguimiento de Procedimientos de Operación de Emergencia";III Congreso Iberoamericano de Inteligencia Artificial; La Habana, Cuba; Febrero de 1992..

RESPONSIBILITY IN THE PROGRAM:

Teaching/Research 100%
Fellowship Program Courses: Nuclear Reactor Technology, Computer Data Structures.

OTHER PERTINENT DATA:

Co-responsible of the Nuclear Engineering Analysis Laboratory. Founder member of the Mexican Nuclear Society since 1988.

Rubén F. Ortega-Carmona

ACADEMIC RANK: Professor

DEPARTMENT AFFILIATION: Energy, National Autonomous University of Mexico (UNAM), College of Engineering.

DEGREES:

B.S., Chemical Engineering, UNAM 1962
M.S. and D.I.C., Nuclear Technology, Imperial College of Science and Technology, Unversity of London 1967

FIELDS OF SPECIALIZATION AND AREAS OF INTEREST:

Nuclear Power Economics, Nuclear Fuel Cycle Technology, Nuclear Power Plant Safety.

RESPONSIBILITY IN THE PROGRAM:

Teaching/Research 100%
Fellowship Program Courses: Nuclear Power Economics, Nuclear Fuel Cycle Technology, Nuclear Power Plant Safety

INDUSTRY EXPERIENCE OR CONSULTING WORK:

Coordinator and Professor of the M. Sc. Program in Nuclear Sciences at the Chemistry Faculty of the University of Mexico, Mexico (1969 up to date). 25 years working at the Laguna Verde Nuclear Power Plant, mainly as Fuel Manager and Head of Nuclear Fuel Supply Department, Commision Federal de Electricidad, Mexico (1970-1996). Participated in the Laguna Verde Project since the initial Call for Bids up to the Operation of the Plant. Consulting for the company COGEMA at Cornell University, for the development of an economic model to study the spent fuel management, USA (1997-98)

OTHER PERTINENT DATA:

Participated as Instructor at the Electric System Expansion Planning Courses at Argonne National Laboratory, organized by the IAEA and ANL, (1978-1981). Fullbright-Hays Visiting Professor at the Nuclear Engineering Department of Iowa State University, USA (1980-81). Professor at the M. Sc. Program in Energy, Post-Graduate Division of the Engineering Faculty of the University of México, México (1985 up to date). Fellowship of the company COGEMA to study the technology for spent fuel management and radwaste treatment for low/medium level wastes in France (1990-91). Member of the Mexican Academy of Engineering since November 1998. Working at present in consulting for the Energy Department and the Nuclear Reactor Engineering Laboratory (LAIRN) of the Engineering Faculty of the University of Mexico (1999 up to date)

Pamela Fran Nelson

ACADEMIC RANK: Researcher

DEPARTMENT AFFILIATION: Energy, National Autonomous University of Mexico (UNAM), College of Engineering.

DEGREES:

B.S., Nuclear Engineering, University of California, Los Angeles, 1982
M.S., Nuclear Engineering, University of California, Los Angeles, 1985

FIELDS OF SPECIALIZATION AND AREAS OF INTEREST:

Probabilistic Risk Analysis, Severe Accident Management, Decision Analysis

SOME RESEARCH PUBLICATIONS:

• Implantación de APS Niveles 1 y 2 en la plataforma computacional Saphire Revisión 0, INFORME TÉCNICO NO. UNAM/FI/DEP/N3-03, Convenio Específico 14306-1156-3-X-03 Comisión Nacional de Seguridad Nuclear y Salvaguardias,10 dic. 2003.
• Barbosa, G., Gutiérrez R., Nelson, P., Chávez, C., "Simulador Docente para Divulgación de la Energía Nuclear", Reunión Anual Sociedad Nuclear Mexicana, Guadalajara, nov. 2003.
• Pamela Nelson, Manuel González, "Las Guías de Procedimientos de Emergencia y de Accidente Severo para Laguna Verde", CFE, 2001.

RESPONSIBILITY IN THE PROGRAM:

Teaching/Research 100%
Fellowship Program Courses: Introduction to Probabilistic Risk Analysis.

RECENT INDUSTRY EXPERIENCE OR CONSULTING WORK:

Mexican Nuclear Regulatory Commission, project to transfer the Laguna Verde Nuclear Plant PRA, Levels 1 and 2, from the R&R platform to SAPHIRE.

OTHER PERTINENT DATA:

Member: SNM (Mexican Nuclear Society).

(19) RUSSIAN FEDERATION

Nikolai N Ponomarev-Stepnoi.

Academician Ponomarev-Stepnoi began his career at the Kurchatov Institute of Atomic Energy as Senior Technician in 1952, after graduating from the Moscow Engineering and Physics Institute. In 1962 he took the position of Deputy Director of the High-temperature Power Systems Department. In 1987 he became the First Deputy Director of the Kurchatov Institute, and since 1992 he has been holding the position of Vice President of the Russian Research Center "Kurchatov Institute".

His research interests are wide-ranging and cover such areas as reactor physics and technology; thermionic energy conversion; nuclear and radiation safety; radiation damage of nuclear materials; non-proliferation; control and accounting of nuclear materials; nuclear fuel cycle (Pu disposition, Th utilization). He is a participant in development of a nuclear aircraft (KAR), a nuclear rocket engine (IVG), a thermionic converter-reactor (Romashka), a space thermionic nuclear power system (Yenisei), high-temperature helium cooled reactors (VG-400, MGR, GT-MHR), a commercial reactor for isotope production, new generation light water reactors (NP-640, VPBER, VVER-m). He received his Doctor Sc. degree in 1964. He published 121 papers and two books: Heat Release in a Nuclear Reactor in 1985, and Nuclear Reactor Profiling in 1988. For his scientific accomplishments he was awarded two prestigious USSR/Russia prizes: Lenin Prize and State Prize.

Since 1971 he has been serving as Professor with the Moscow Aviation Institute (Technical University). He heads the Chair of Nuclear Processes Modeling at the Moscow Physics and Technical Institute, and the Branch Chair of Aircraft Engines at the Moscow Aviation Institute.

He has been the full member of the Russian Academy of Sciences since 1987. At the Academy he chairs the Research Council on Nuclear Power.

He served as President of the Russian Nuclear Society in 1992-1993, and was the member of the ANS Board of Directors in 1999-2001.

Academician Nikolai N Ponomarev-Stepnoi, Prof.
Vice President
Russian Research Center "Kurchatov Institute"
1 Kurchatov Square
Moscow 123182
Russia

Tel: 7 (095) 196-9066
Fax: 7 (095) 943-0074
E-mail: niknik@kiae.ru

Aleksei Borisovich Korostelev.

Professor Korostelev started his nuclear career in the Research and Development Institute of Power Engineering, Moscow, in 1986, after graduating from the Moscow Institute of Steel and Alloys. He worked in RDIPE as a Senior Scientist till 1998.

In 1998 he was invited to Minatom to take two posts:

• Scientific Secretary of the Expert Council of the Higher Certifying Commission at Minatom (now the Federal Agency of Atomic Energy) and
  
  
• Scientific Secretary of "Nuclear Technologies" Section of the Russian Government Council on Awards in Science and Technology.
  

He is still holding both posts.

In 2000 he earned doctor's degree in Technical Sciences (his doctorate was devoted to production and processing of steels and alloys for nuclear power facilities components).

In 2001-2003 he was the Head of the Directorate for Support of Minatom S & T Council Activities, and studied in the Russian Academy of State Service (President's Administration) which he graduated from in 2003. In the same period, in 2002, he became a certified Professor.

Starting from 2003 he is a Chief Expert in the Nuclear Science & Technology Department of Minatom of Russia (now the Nuclear Science & Technology Directorate of the Federal Agency of Atomic Energy).

His experience and research interests include nuclear power facilities (designing, operation and decommissioning) for various purposes, thermonuclear reactor ITER, components strength calculation, materials science in machine building, metals science and metals heat treatment.

He has 67 research papers and inventor's certificates.

A winner of the Russian Government Award in Science & Technology.

Prof. A.B. Korostelev,
Chief Expert of NSTD, FAAE
Bolshaya Ordynka 24/26
Moscow 119017
Russia

Phone: 7 (095) 239 4470
Fax: 7 (095) 951 5073
E-mail: akorostelev@minatom.net

Professor Shmelev works in Moscow Engineering and Physics Institute (Chair of Theoretical and Experimental Physics of Nuclear Reactors). He started his research career in MEPhI in 1969, 20 years later got a technical sciences doctor's degree (his doctorate was "Nuclear Power Facilities"), and in 1992 became a full professor.

Prof. Shmelev's experience and research interests include fast reactors physics, fuel cycles physics, long-lived radwaste disposal physical problems, electronuclear and thermonuclear facilities for waste disposal, neutron physics of electronuclear and thermonuclear facilities, nuclear fuel and waste processing, fuel deep burn-up, denatured plutonium, thorium-uranium mixed cycle.

Major books and publications:
Fast Neutron Reactors in Breeder Mode (1971);
Some Issues Concerning the Physics of Fuel Breeding in Fast Neutron Breeder Reactors (1979);
Use of Thorium in Nuclear Reactors (1983);
Equilibrium, Proliferation Resistant, Closed Fuel Cycles for LWRs (Safety Issues Associated with Plutonium Involvement in the Nuclear Fuel Cycle. - NATO Science Series. Series 1: Disarmament Technologies - Vol. 23, 1999)
Nuclear Technologies (2001)
Physical Principles of Long-Lived Radwaste Disposal (Neutron Transmutation) (2002).

Prof. A.N. Shmelev
Moscow Engineering and Physics Institute (MEPhI)
Chair of Theoretical and Experimental Physics of Nuclear Reactors
Kashirskoe Shosse 31
Moscow 115409
Russia

Phone: 7 (095) 323 9242
Fax: 7 (095) 324 7026
E-mail: shmelev@nr.mephi.ru

Nikolai Egorovich Yakovlev.

Since 1999, Prof. Yakovlev is a Director General of the Federal State Unitary Enterprise "Central Research Institute of Management, Economics & Information" (FSUE "ATOMINFORM") of Minatom (now Federal Afency of Atomic Energy) of Russia.

His career in science started in 1966, when after graduating from the Tomsk State University (TSU) in Siberia, he continued his studies in the TSU and became a reader in 1968.

In 1971 he was invited to work in the Institute of Atmosphere Optics (Siberian Division of the USSR Academy of Sciences) conveniently in the same city of Tomsk. His first research paper was published the same year. His interests covered mathematics, cybernetics and computer systems.

In 1985 he earned a doctor's degree in physics and mathematics. At that time he was already reading (as a parallel job) in the Tomsk Polytechnical Institute (TPI), where in 1987 he became a certified professor in applied mathematics.

He continued to work in the IAO and TPI till 1989. He had already 8 research publications and coauthored 86 more.

In 1989 he was invited to Moscow to work in the Research and Development Institute of Power Engineering (RDIPE). The same year he moved to Moscow. He headed one of RDIPE departments until, in 1999, the Minister of Atomic Energy of Russia assigned him another job - to head the Central Research Institute of Management, Economics & Information of Minatom.

Among awards and honors bestowed on Prof. Yakovlev two deserve special mentioning:

• Government Award - "Badge of Honor" (1986) and
  
• Government Prize in Science & Technology Nominations for his research work: "Development, Production and Adoption of Nuclear-Physical Systems for Fast Multi-Element Analysis of Substances & Materials" (2004).

Prof. N. E. Yakovlev
Director General of FSUE "ATOMINFORM"
Dmitrovskoye Shosse 2
Moscow 127434
Russia

Phone: 7 (095) 777 9688
Fax: 7 (095) 777 9680
E-mail: yakovlev@ainf.ru

(20) SOUTH AFRICA

(21) SPAIN

(22) SWEDEN

Tomas Lefvert.

Tomas Lefvert is Corporate Scentific Adviser at Vattenfall AB (www.vattenfall.com) and adjunct professor in Reactor Physics at the Royal Institute of Technology in Stockholm (www.kth.se). At Vattenfall he has been managing departments in the areas of nuclear fuel technology, safety analysis, computer code development and in-core fuel management. He is presently Director of the Swedish Centre of Nuclear Technology (www.nuclear-tech-centre.org), an organisation supporting research and education in nuclear technology at the main technical universities in Sweden. On the international arena he is the present chairman of the OECD NEA Nuclear Science Committee (www.nea.fr), member of the OECD NEA Committee on the Safety of Nuclear Installations and the Swedish representative to the European Atomic Energy Society.

Tomas Lefvert
Professor
Swedish Centre for Nuclear Technology
Department of Physics
Royal Institute of Technology
Alba Nova University Centre
106 91 Stockholm, Sweden
Tel: +46-8 5537 8225
Fax: +46-8 20 80 76
Email: tomas@physics.kth.se
www.nuclear-tech-centre.org

(23) UNITED KINGDOM

Philip J Thomas.

Professor Thomas gained 25 years' experience working in the chemical and nuclear industries before joining City University in August 2000. His initial posting was with ICI, where spent 5 years developing control systems for large chemical plant, making extensive use of techniques for dynamic simulation. He then joined the UKAEA/ AEA Technology, where headed up Departments concerned with: C&I product development for nuclear and non-nuclear use, non-destructive testing technology and materials research, and research into remote handling and nuclear decommissioning, where he was Customer Project Manager for the decommissioning to green-field of the 100MWth/33MWe Windscale AGR.

His research interests are wide-ranging and he has published over 50 papers on control, instrumentation, nuclear decommissioning, risk assessment and project management. The Institute of Measurement and Control awarded him its prestigious ICI Prize in 1984, 1987 and 1997. His book, Simulation of Industrial Processes for Control Engineers, published in 1999, has been praised by reviewers as the new standard text for practitioners of dynamic simulation. His work on in risk analysis and management has excited the interest of the national and international press, and he has given several radio and television interviews.

He is a Member of the Academic Board of the Royal Navy's Department of Nuclear Science and Technology and is a member of the Board of Trustees of the British Nuclear Energy Society. He is Associate Editor of the Transactions of the Institute of Measurement and Control. He represents the Inst.M.C. on the Executive Committee of the United Kingdom Automatic Control Council, the National Member Organisation of the International Federation of Automatic Control. He is chairman of the Nuclear Academia-Industry Liaison Society (NAILS), the body that promotes the interchange of information between universities and the nuclear industry in the UK.

He was President of the Institute of Measurement and Control from January 2001 to January 2002 and currently serves on that body's Council as Past President.

Professor Philip J Thomas, BSc, CEng, FIEE, FInstMC
Professor of Engineering Development and Director of the Centre for Risk Management, Reliability and Maintenance
School of Engineering and Mathematical Sciences
City University
Northampton Square
London EC1V 0HB
Email: P.J.Thomas@city.ac.uk

Paul O'Brien.

Since 1999 Paul O'Brien has held the chair of Inorganic Materials Chemistry at the University of Manchester- spanning both the Chemistry Department and the Manchester Materials Science Centre.

He is head of the Chemistry Department. Previously Paul has held professorial positions at Imperial and Queen Mary and Westfield Colleges and has been a visiting professor at Georgia Institute of Technology. Paul has a strong interest in developing countries and advised Mahanakorn University of Technology (Thailand) and leads a Royal Society programme at the University of Zululand, South Africa.

His research interests concern the development of novel chemical routes for the deposition of materials especially sulphur or selenium containing compounds). The materials are prepared both as thin films and isolated quantum dots.

Paul has published over 350 papers and is the author and editor of several monographs. As a strong advocate of communicating science to a wider audience, Paul gives an increasing number of popular or cross-cultural science lectures - usually on nanotechnology. He has spoken at the Institute of Contemporary Arts and the V and A Museum, given several radio interviews and run master-classes for school children.

He is Chairman of the Materials Forum of the Royal Society of Chemistry. In 2003 he was Chemistry President of the British Association Meeting.

Since 2001 he has led for the University of Manchester a project to develop and over arching structure to facilitate research teaching and training in nuclear sciences and engineering. More recently this activity has been expanded to include UMIST with whom the New University of Manchester will be formed in 2004.

He will happily field any enquiries for concerning nuclear sciences and engineering in Manchester and can be reached at paul.obrien@man.ac.uk.

(24) USA

William E. Burchill.

William E. Burchill is Head of the Nuclear Engineering Department, HTRI Professor, and Director of the Texas Engineering Experiment Station Nuclear Engineering Division at Texas A&M University. Texas A&M has the largest nuclear engineering department in the United States. Dr. Burchill's experience and research interests include nuclear safety, risk management, nuclear power, reactor regulation, reactor operations, and reactor design.

Dr. Burchil was Director, Risk Management with Exelon Nuclear in Chicago, Illinois from 1998 through 2002. He led and facilitated risk management (PRA) practices in decision making at the Exelon corporate and regional offices and ten nuclear plant sites involving seventeen operating nuclear power plants. During this period, he was a member of the Nuclear Energy Institute Risk Based Applications Task Force, met with the U.S. Nuclear Regulatory Commission many times relative to the NRC Risk Informed Regulation Initiative, and was a member of the BWR Owners Group Integrated Risk Informed Regulation Subcommittee.

From 1995 through 1997, Dr. Burchill was Manager, Nuclear Assessment Services with Pennsylvania Power & Light, Allentown, PA where he led self-assessment initiatives and was responsible for independent safety review, operating experience application, and quality assurance. From 1970 to 1994 he was with ABB Combustion Engineering holding the positions of Project Director, Engineering Operations; Director, Operations and Field Engineering Services; Director, Nuclear Training; Manager, C-E Owners Group Programs; Manager, C-E ATWS Task Force; Section Manager, ECCS Analysis Development; Supervisor, NSSS Simulation; and Supervisor, Small Break LOCA Analysis.

He earned a B.S. in Metallurgical Engineering (Nuclear Option) from the Missouri School of Mines & Metallurgy in 1964; M.S. and Ph.D. degrees in Nuclear Engineering from the University of Illinois in 1965 and 1970, respectively; and an M.S. in Management from the Rensselaer Polytechnic Institute Hartford Graduate Center in 1986.

Dr. Burchill has been an Invited Lecturer in IAEA/ANL courses on "Nuclear Safety" in 2000 through 2002; in the INPO/MIT "Reactor Technology Course for Utility Executives" in 1993 through 2002; in the Northwestern University "Safety of Light-Water-Cooled Nuclear Power Plants" course in 1982 through 1987; and in the "Advanced Course of Nuclear Reactor Safety Assessment," sponsored by the University of Beograd International Center for Heat and Mass Transfer in Dubrovnik, Yugoslavia in 1981. He was an Adjunct Lecturer on Nuclear Reactor Safety Control at the RPI Hartford Graduate Center in 1984 and a Visiting Associate Professor of Nuclear Engineering at Texas A&M University in 1982-83.

Dr. Burchill is active in the American Nuclear Society having been a member of the Board of Directors and the Executive Committee, Finance Committee Chair, Special Initiatives Committee Chair, Professional Divisions Committee Chair, Nuclear Installations Safety Division Chair, Nuclear Reactor Safety Division Chair, and Education & Training Division Chair. He has served on the Program Committee for ANS Topical Meetings sponsored by the Nuclear Installations Safety and Reactor Safety Divisions in 1977, 1983, 1986, 1988, 1991, 2002, and 2003. He is currently is a member of the ANS Local Sections and Business Practices Committees and the ANS Low Power/Shutdown PRA Standard Working Group.

(25) EUROPEAN NUCLEAR ENGINEERING NETWORK (ENEN)

William D'haeseleer (see listing under Belgium).

(1) IAEA

Pier Roberto Danesi.

Pier Roberto Danesi, presently Scientific Advisor to the IAEA Deputy Director General, Department of Nuclear Sciences and Applications, has been Director of the IAEA's Laboratories from 1986 to 2001, a multi-disciplinary centre performing research and development, providing scientific services and training nuclear scientists in the frame of the IAEA's programmes in non-power applications of several nuclear technologies (nuclear medicine, industrial development, nuclear instrumentation, management of water resources, food and agriculture, environmental monitoring, radioanalytical chemistry, radiation dosimetry, radiation protection and safeguards verification). Formerly he was Senior Scientist (1982-1986) at Argonne National Laboratory (USA), Director of the Physical and Nuclear Chemistry Laboratory (1975-1981) and Head of the Nuclear and Fuel Reprocessing Chemistry Unit (1966-1974) at the Nuclear Materials Division of the Italian Atomic Energy Commission.

He received his Doctor Degree in Physical-Inorganic-Chemistry at the University of Rome, Italy, in 1962.

He has been member of international committees and scientific leader of international projects dealing with various nuclear and nuclear related issues, such as (i) European Union Committee for the Management of the Hydrogen Programme, (ii) Committee for Separation Science and Technology of the US National Research Council, (iii) Task Force for the UN Sustainable Industrial Development Programme for South-East Asia, (iv) IAEA Senior Expert and IAEA Responsible Scientist for the radiological, morphological and chemical characterisation and analysis of Depleted Uranium (DU) present in the environment as a result of its use in conflicts (Balkans, Gulf War), (v) IAEA Team Leader and Senior Expert of the International Group that conducted the radiological assessment at the nuclear weapon test sites in the Algerian Sahara desert, (vi) Scientific Secretary and IAEA responsible scientist for the study of residual radioactivity in the terrestrial environment in the International Project for the Assessment of the Radiological Situation at the French nuclear weapon test sites in the Pacific region.

He has been Professor at the Universities of Padova and Sassari, Italy, (Chemistry and Technology of Nuclear Material) and Linz, Austria, (Application of Radiation and Isotopes in Industry, Health, Environment and Basic Studies) and, since 1998 till present, at the University of at Pavia (Master Courses in "Nuclear and Ionising Radiation Technology" and "Radiation, Technological and Other Everyday Risks in the Modern Society").

He has received scientific awards (two) from the Royal Society (UK) and Accademia Italiana dei Lincei (Italy) and from the Deutsche Gesellshaft fuer Chemisches Apparatwesen, Chemische Tecknik und Biotechnologie e.v. and the UK Society of Chemical Industry.

His present major fields of interest are comparative risk assessments and environmental monitoring and protection. His research work and experience covers the chemistry of the reprocessing and fabrication of nuclear fuel, processing of nuclear wastes, basic solution chemistry of actinides, applications of radiation and isotopes to environmental, industrial and agricultural studies, environmental assessments related to the presence of residual radioactivity at former nuclear test and armed conflicts sites, application of radioisotopes to the study the kinetics of chemical reactions, mass transfer problems, transport across membranes, environmental radiochemistry, radiochemical separations.

He has published about 150 scientific papers and four book chapters.