HTGR Knowledge Base

IAEA-TC--389.26: Gas-cooled reactor technology safety and siting

Technical committee meeting on gas-cooled reactor technology safety and siting Dimitrovgrad (Russian Federation) 21-23 Jun 1989

International Atomic Energy Agency, Vienna (Austria), IAEA-TC--389.26

Abstract

The Technical Committee Meeting (TCM) consisted of fife half-day sessions with the papers grouped into five different categories:

The technical content of most of the papers presented at the meeting has been incorporated in the IAEA report: Technical Report Series No 312 'Gas Cooled Reactor Design and Safety', May 1990. The Table of Contents of this report is given in Appendix II. In addition, about one-half of the papers have been included in a special issue of Energy, the international journal dedicated to High Temperature Gas-cooled Reacotrs. The Table of Contents of this special issue is given in Appendix III.

The meeting report summarizes the Technical Committee Meeting in terms of the program in each country as an overview of all of the papers presented by the authors from each country.

The papers presented at the TCM are included without editing.

view the full text of this conference report (format: PDF, size= 29485kB, 724 pages)

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Articles

Safety concept of high-temperature reactors based on the experience with AVR and THTR
Wachholz, Winfried (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany)); Kroeger, Wolfgang (Institut fuer Nukleare Sicherheitsforschung, Kernforschungsanlage Juelich (Germany))

Depressurization accident analysis for the HTTR by the TAC-NC
Kunitomi, K.; Nishiguchi, I.; Wada, H.; Takeda, T.; Hishida, M.; Sudo, Y.; Tanaka, T.; Saito, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)

Calculation studies of behaviour of HTGR spherical fuel elements during an acident induced by a high-positive reactivity fast introduction
A.O. Gol'tsev

MHTGR radionuclide source terms for use in siting
Inamati, S.B.; Neylan, A.J.; Silady, F.A. (General Atomics, San Diego, CA (United States)); Walker, L.L. (SWEC, United States (United States))

Transfer of fissile material through shielding coatings in emergency heating of HTGR coated particles
Gudkov, A.N.; Zhuravkov, S.G.; Koptev, M.A.; Kurepin, A.D

Analytical method and result of off-site exposure during normal operation of high-temperature engineering test reactor (HTTR)
Sawa, K.; Mikami, H.; Saito, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)

Advanced gas cooled reactors - Designing for safety
Keen, Barry A. (Engineering Development Unit, NNC Limited, Booths Hall, Knutsford, Cheshire (United Kingdom))

Structure-stable alloy for structural components of the high-temperature gas-cooled reactor with coolant temperature of 950 deg C
Dushin, Y.A.; Gribov, N.N.; Ignatov, V.A.; Medvedev, N.A. (Experimental and Industrial Enterprise ''Prometey'', Leningrad (USSR))

Main principles of low-power HTGR radiation safety ensurance
Bylkin, B.K.; Grebennik, V.N.; Kirjushin, A.I.; Kuzovkov, N.G.; Ponomorjev-Stepnoi, N.N.; Hruljev, A.A.; Yanushevich, I.V

Design status of the HTR 500 power plant and the HTR module power plant
Arndt, E.; Fischer, R. (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany, F.R.))

High temperature technological heat exchangers and steam generators with helical coil assembly tube bundle
Korotaev, O.J.; Mizonov, N.V.; Nikolaevsky, V.B.; Nazarov, E.K

The choice of equipment mix and parameters for HTGR-based nuclear cogeneration plants
Malevski, A.L.; Stoliarevski, A.Ya.; Vladimirov, V.T.; Larin, E.A.; Lesnykh, V.V.; Naumov, Yu.V.; Fedotov, I.L

Prospects for application of high-temperature helium reactor (HTHR) to provide for power needs in refineries and petrochemical plants
Feigin, E.A.; Raud, E.A.; Romanova, E.G.; Panasenko, P.A.; Nikitin, V.N

Neutron-physical aspects of the HTR concept with spherical fuel elements
Ponomarev-Stepnoy, N.N.; Grebennik, V.N.; Glushkov, E.S.; Kucharkin, N.E

Improved safety nuclear power - and - heating plant with HTGR of modular type
Bogoyavlenskii, R.G.; Vinogradov, V.P.; Glebov, V.P.; Grebennik, V.N.; Ponomarev-Stepnoi, N.N.; Hruljov, A.A

Utilization of process heat from the HTR in the chemical and related industries
Schad, M.; Didas, U.; Ebeling, F.; Kreutzkamp, G.; Renner, H

Safety assessment principles for reactor protection systems in the United Kingdom
Philp, W

Design and safety consideration in the high-temperature engineering test reactor (HTTR)
Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)

The design status of the United States Department of Energy modular high temperature gas cooled reactor
Mills, Raymond R. Jr. (Modular High Temperature Gas Cooled Reactor Plant Design Control Office (United States))

UK regulatory aspects of prestressed concrete pressure vessels for gas-cooled reactor nuclear power stations
Watson, P.S. (HM Nuclear Installations Inspectorate (HMNII), Health and Safety Executive (United Kingdom))

Possible applications of HTGR's in Turkey
Atak, S. Metin (Turkish Atomic Energy Authority, Nuclear Safety Department (Turkey))

An economic assessment of the U.S. MHTGR design
Mears, L.D. (Gas-Cooled Reactor Associates, San Diego, CA (USA))

The HTR, applications, economics and environmental aspects
Barnert, H. (Nuclear Research Center Juelich, Institute for Reactor Development, Juelich (Germany)); Schad, M. (Lurgi GmbH, Frankfurt (Germany)); Candeli, H. (Interatom, Bensberg (Germany))

Problems of attracting nuclear energy resources in order to provide economical and rational consumption of fossil fuels
Nazarov, E.K.; Nikitin, A.T.; Ponomarev-Stepnoy, N.N.; Protsenko, A.N.; Stolyarevskii, A.Ya.; Doroshenko, N.A. (State Institute of Nitrogen Industry, Moscow (USSR); I.V. Kurchatov Institute of Atomic Energy, Moscow (USSR))

Assessment of the licensing aspects of HTGR in Yugoslavia
Varazdinec, Z. (Institut za Elektroprivredu-Zagreb, Zagreb (Yugoslavia))

Substantiation of choice of the main physical and thermohydraulic parameters of reactor plant with small power HTGR
Afanasyev, V.N.; Golovko, V.F.; Zhigulsky, V.N.; Karpov, V.A.; Kiryushin, A.I.; Kuzavkov, N.G.; Sukharev, Yu.N

Radiation resistance of pyrocarbon-boned fuel and absorbing elements for HTGR
Gurin, V.A.; Konotop, Yu.F.; Odejchuk, N.P.; Shirochenkov, S.D.; Yakovlev, V.K. (Kharkov Institute of Physics and Technology, Ukrainian SSR, Academy of Sciences, Kharkov (USSR)); Aksenov, N.A.; Kuprienko, V.A.; Lebedev, I.G.; Samsonov, B.V. (V.I. Lenin Nuclear Reactor Research Institute, Dimitrovgrad (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
Nickel, H. (Kernforschungsanlage Juelich GmbH, Juelich (Germany); RWTH Aachen (Germany)); Bodmann, E. (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany)); Seehafer, H.J. (Interatom GmbH, Bergisch-Gladbach (Germany))

Research and Development programs for HTGRs in JAERI
Nishiguchi, Isoharu; Saito, Sinzo (Department of HTTR Project, Japan Atomic Energy Research Institute (Japan))

Behaviour of HTGR coated fuel particles at high-temperature tests
Chernikov, A.S.; Lyutikov, R.A.; Kurbakov, S.D.; Repnikov, V.M.; Khromonozhkin, V.V.; Soloviyov, G.I

Present status of MHTGR program in USA
Millunzi, A. (comp.) MHTGR Program Team

LEU-HTR critical experiment program for the PROTEUS facility in Switzerland
Brogli, R.; Bucher, K.H.; Chawla, R.; Foskolos, K.; Luchsinger, H.; Mathews, D.; Sarlos, G.; Seiler, R. (Paul Scherrer Institute, Laboratory for Reactor Physics and System Technology Wuerenlingen and Villigen, Villigen PSI (Switzerland))

Present status of research and development for HTR in China
Wang Dazhong; Zhong Daxin; Xu Yuanhul (Institute of Nuclear Energy Technology, Tsinghua University, Beijing (China))

The prospects of HTR plant in China
Ye Liangcheng

Czechoslovak approach to the potential of HTGRs' introduction
Jakesova, L.; Podest, M. (Nuclear Research Institute, Rez (Czechoslovakia)); Pinkas, V. (Czechoslovak Atomic Energy Commission, Prague (Czechoslovakia)

Results and future programme of HTR's study
Mursid Djokolelono; Soedyartomo Soentono (National Atomic Energy Agency (Indonesia))

Reactor tests and post-reactor examination of HTGR fuel elements and coated particles
Degaltsev, Yu.G.; Khrulev, A.A.; Mosevitskii, I.S.; Ponomarev-Stepnoi, N.N.; Tikhonov, N.I.; Yakovlev, V.V. (I.V. Kurchatov Institute of Atomic Energy, Moscow (USSR))

Structural graphite for high-temperature gas-cooled reactors
Virgiliev, Yu.S.; Avramenko, P.Ya.; Grebennik, V.N.; Kalyagina, I.P.; Lebedev, I.G.; Filimonov, V.A.; Shurshakova, T.N