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Reactor Technology Safety and Siting XA0101477-5/I5* IAEA-TC-389.26 LIMITED DISTRIBUTION REACTOR TECHNOLOGY SAFETY AND SITING REPORT OF A TECHNICAL COMMITTEE MEETING ORGANIZED BY THE INTERNATIONAL ATOMIC ENERGY AGENCY AND HELD IN DIMITROVGRAD, USSR, 21-23 JUNE 1989 Reproduced by the IAEA Vienna, Austria, 1990 NOTE The material in this document has been supplied by the authors and has not been edited by the IAEA. The views expressed remain the responsibility of the named authors and do not necessarily reflect those of the govern- ments) of the designating Member State(s). In particular, neither the IAEA nor any other organization or body sponsoring this meeting can be held responsible for any material reproduced in this document. FOREWORD On the invitation of the Government of the Union of Soviet Socialist Republics, the Eleventh International Conference on the HTGR and the IAEA Technical Committee Meeting on Gas-Cooled Reactor Technology, Safety and Siting were held in Dimitrovgrad, USSR, on June 21-23, 1989. The meetings complemented each other. Due to the large worldwide interest, the conference attracted approximately 60 participants from 18 countries and 130 Soviet delegates. About 50 foreign participants and 100 Soviet delegates stayed over for the Technical Committee Meeting. The Technical Committee Meeting provided the Soviet delegates with an opportunity to display the breadth of their program on HTGR's to an international audience. Nearly one-half of the papers were presented by Soviet participants. Among the highlights of the meeting were the following: - The diverse nature and large magnitude of the Soviet research and development program on high temperature gas-cooled reactors. Over 35 different research and design institutes were represented by the Soviet participants. - The,Government approval of the budget for the construction of the 30 MWt High Temperature Test Reactor (HTTR) in Japan. The schedule contemplates a start of construction in spring 1990 on a site at the Oarai Research Establishment and about a five year construction period. Japan also announced that a symposium on HTGR Technologies would be held on March 19-20, 1990 in Tokyo to commemorate the start of construction of the HTTR, with plans to hold such a symposium every three years. - Disappointment in the announced plans to shutdown both the Fort St. Vrain (FSV) plant in the United States (US) and the Thorium High Temperature Reactor (THTR-300) in Germany. These two reactors presently represent the only operating HTGRs in the world since the AVR plant in Jiilich, Germany, was also shutdown at the end of 1988. - The continuing negotiations between Germany and the USSR on the terms of the co-operation between the two countries for the construction of a HTR Module supplemented by joint research and development activities aimed at increasing coolant outlet temperatures from 750°C to 950°C. - The continued enthusiasm displayed by both the US and German representatives for the potential of the small modular designs under development in both countries and the ability for these designs to meet the stringent requirements demanded for the future expansion of nuclear power. - The combining of the HTGR technology interest of ABB-Atom and Siemens in Germany into a joint enterprise, HTR GmbH, in May 1989. - The generally favorable review of the unique safety aspects of the US MHTGR design by the US. Nuclear Regulatory Commission (NRC) in their draft Safety Evaluation Report which was issued in February, 1989. - The increasing interest by gradually more and more industrializing countries and even a few new industrialized countries in incorporating MHTGRs into their plans for expanded electricity production and for enhanced oil recovery and district heating. - 2 - Most of the papers provided an expansion of views or details of the development work supporting the national programs or perspectives outlined during the preceding International Conference. Apparent throughout was the gradually increasing effort taking place in the world to support the modular HTGR and the recognition that the demonstration of its unique characteristics is the logical next step in commercialization of the concept. The view expressed by industrializing countries in terms of application studies, siting and licensing aspects and by industrialized countries in terms of design and development progress, project prospects, cost analyses and long range technological growth potential into higher temperature industrial applications provided substantial evidence to this increasing recognition. ************ 8974p LIST OF CONTENTS MEETING REPORT 7 APPENDIX I - List of Participants 12 APPENDIX II - Table of Contents IAEA TR 312 24 APPENDIX III - Table of Contents, Special Issue of Energy, The International Journal 27 TECHNICAL COMMITTEE MEETING PAPERS SAFETY CONSIDERATIONS (Session A) Safety Concept of High-Temperature Reactors Based on the Experience with AVR and THTR A-l W. Wachholz, W. Kroger - Federal Republic of Germany Depressurization Accident Analysis for the HTTR by the TAC-NC A-2 K. Kunitomi, I. Nishigushi, T. Takeda, M. Hishida, Y. Sudo, T. Tanaka, S. Saito - Japan Calculation Studies of Behaviour of HTGR Spherical Fuel Elements During an Accident Induced by a High-Positive Reactivity Fast Introduction A-3 A.O. Gql'tsev - USSR MHTGR Radionuclide Source Terras for Use in Siting A-4 S.B. Inamati, A.J. Neylan, F.A. Silady, L.L. Walker - USA Transfer of Fissile Material through Shielding Coatings in Emergency Heating of HTGR Coated Particles A-5 A.N. Gudkov, S..G. Zhuravkov, M.A. Koptev, A.D. Kurepin - USSR Analytical Method and Result of Off-Site Exposure during Normal Operation of High Temperature Engineering Test Reactor (HTTR) A-6 K. Sawa, H. Mikami, S. Saito - Japan Advanced Gas-Cooled Reactors - Designing for Safety A-7 B.A. Keen - United Kingdom Structure Stable Alloy for Large-sized Equipment of High Temperature Gas Cooled Reactor with Coolant Temperature of 950°C A-8 Y.A. Dushin, N.N. Gribov, V.A. Ignatov, N.A. Medvedev - USSR Main Principles of Low-Power HTGR Radiation Safety Ensurance A-9 B.K. Bylkin, V.N. Grebennik, A.I. Kirjushin, N.G. Kuzovkov, N.N. Ponomarev-Stepnoi, A.A. Hruljev, I.V. Yanushevich - USSR PROJECT PROSPECTS (Session B) Design Status of the HTR-500 Power Plant and the HTR Module Power Plant B-l E. Arndt, R. Fisher - Federal Republic of Germany High Temperature Technological Heat Exchangers and Steam Generators with Helical Coil Assembly Tube Bundle B-2 O.J. Korotaev, N.V. Mizonov, V.B. Nikolaevsky, E.K. Nazarov, - USSR - 2 - The Choice of Equipment Mix and Parameters for HTGR-Based Nuclear Cogeneration Plants B-3 A.L. Malevski, A.Ya. Stoliarevski, V.T. Vladimirov, E.A. Larin, V.V. Lesnykh, Yu.V. Naumov, I.L. Fedotov - USSR Prospects for Application of High-temperature Helium Reactor (HTHR) to Provide for Power Needs in Refineries and Petrochemical Plants B-4 E.A. Feigin, E.A. Raud, E.G. Romanova, P.A. Panasenko, V.N. Nikitin, - USSR Neutron-Physical Aspects of the HTR Concept with Spherical Fuel Elements B-5 N.N. Ponomarev-Stepnoi, V.N. Grebennik, E.S. Glushkov, N.E. Kucharkin - USSR DESIGN STATUS (Session C) Improved Safety Nuclear Power - and - Heating Plant with HTGR of Modular Type C-l R.G. Bogoyavlenskii, V.P. Vinogradov, V.P. Glebov, V.N. Grebennik N.N. Ponomarev-Stepnoi, A.A. Hruljov - USSR Utilization of Process Heat from the HTRM in the Chemical and Related Industries C-2 M. Schad, H. Barnert, R. Candeli - Federal Republic of Germany Safety Assessment Principles for Reactor Protection Systems in the United Kingdom C-3 W. Philp - United Kingdom Design and Safety Consideration in the High-Temperature Engineering Test Reactor (HTTR) C-4 S. Saito, T. Tanaka, Y. Sudo, 0. Baba, S. Shiozawa, M. Okubo - Japan The Design Status of the United States Department of Energy Modular High Temperature Gas Cooled Reactor C-5 Raymond R. Mills - USA UK Regulatory Aspects of Prestressed Concrete Pressure Vessels for Gas-Cooled Reactor Nuclear Power Stations C-6 P.S. Watson - United Kingdom COST AND ECONOMIC ASPECTS (Session D) Possible Applications of HTGR's in Turkey D-l S. Metin Atak - Turkey An Economic Assessment of U.S. MHTGR Design D-2 L. Daniel Mears - USA The HTR, Applications, Economics and Environmental Aspects D-3 H. Barnert, M. Schad, H. Candeli - Federal Republic of Germany Problems of Attracting Nuclear Energy Resources in order to provide Economical and Rational Consumption of Fossil Fuels D-4 E.K. Nazarov, A.T. Nikitin, N.N. Ponomarev-Stepnoi, A.N. Protsenko, A.Ya. Stolyarevskii, N.A. Doroshenko - USSR - 3 - Assessment of the Licensing Aspects of HTGR in Yugoslavia D-5 Z. Varazdinec - Yugoslavia Substantiation of Choice of the Main Physical and Thermohydraulic Parameters of Reactor Plant with small Power HTGR D-6 V.N. Afanasyev, V.F. Golovko, V.N. Zhigulsky, V.A. Karpov, A.I. Kiryushin, N.G. Kuzavkov, Yu.N. Sukharev - USSR RESEARCH AND DEVELOPMENT (Session E) Radiation Resistance of Pyrocarbon-Bonded Fuel and Absorbing Elements for HTGR E-l V.A. Gurin, Yu.F. Konotop, N.P. Odejchuk, S.D. Shirochenkov, V.K. Yakovlev, N.A. Aksenov, V.A. Kuprienko, I.G. Lebedev, B.V. Samsonov - USSR The Materials Programme for the High-Temperature Gas-Cooled Reactor in the Federal Republic of Germany: Status of the development of high-temperature materials, integrity concept, and design codes E-2 H. Nickel, E. Bodmann, H.J. Seehafer - Federal Republic of Germany Research and Development Programs for HTGRs in JAERI E-3 I. Nishiguchi, S. Saito - Japan Behaviour of HTGR Coated Fuel Particles at High-Temperature Tests E-4 A.S. Chernikov, R.A. Lyutikov, S.D. Kurbakov, V.M. Repnikov, V.V. Khromonozhkin, G.I. Soloviyov - USSR Present Status of MHTGR Program in USA E-5 A. Millunzi - USA LEU-HTR Critical Experiment Program for the PROTEUS Facility in Switzerland E-6 R.
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