HTGR Knowledge Base

IWGGCR--25: Behaviour of gas cooled reactor fuel under accident conditions.

Behaviour of gas cooled reactor fuel under accident conditions. Proceedings of a specialists meeting held in Oak Ridge, 5-8 November 1990

International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors, IWGGCR--25

Abstract

The Specialists Meeting on Behaviour of Gas Cooled Reactor Fuel under Accident Conditions was convened by the International Atomic Energy Agency on the recommendation of the International Working Group on Gas Cooled Reactors. The purpose of the meeting was to provide an international forum for the review of the development status and for the discussion on the behaviour of gas cooled reactor fuel under accident conditions and to identify areas in which additional research and development are still needed and where international co-operation would be beneficial for all involved parties. The meeting was attended by 45 participants from France, Germany, Japan, Switzerland, the Union of Soviet Socialists Republics, the United Kingdom, the United States of America, CEC and the IAEA. The meeting was subdivided into five technical sessions: Summary of Current Research and Development Programmes for Fuel. Fuel Manufacture and Quality Control. Safety Requirements. Modelling of Fission Product Release - Part I and Part II. Irradiation Testing/Operational Experience with Fuel Elements. Behaviour at Depressurization, Core Heat-up, Power Transients. Water/Steam Ingress - Part I and Part II. 22 papers were presented. A separate abstract was prepared for each of these papers. At the end of the meeting a round table discussion was held on Directions for Future R and D Work and International Co-operation.

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Articles

Overview of current research and development programmes for fuel in Japan
Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)

HTGR programme in the United States of America
Fox, J.E. (USDOE, Washington, DC (United States))

French programme for HTR fuel
Gillet, R.M. (CEA Centre d'Etudes Nucleaires de Grenoble, 38 (France))

HTR fuel element development in the Federal Republic of Germany
Balthesen, E. (Forschungszentrum Juelich GmbH (Germany))

Review of current work on investigation of HTGR fuel in the Union of Soviet Socialist Republics
Grebennik, V.N. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Inst. Atomnoj Ehnergii)

Safety requirements and research and development on HTTR fuel
Saito, S.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai Research Establishment, Oarai, Ibaraki (Japan). Dept. of HTTR Project); Fukuda, K.; Kondo, T. (Japan Atomic Energy Research Inst., Tokai Research Establishment, Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research)

Production process and quality control for the HTTR fuel.
Yoshimuta, S.; Suzuki, N.; Kaneko, M. (Nuclear Fuel Industries, Ltd, Tokai, Ibaraki (Japan)); Fukuda, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)

Modelling of fission product release behavior from HTR spherical fuel elements under accident conditions.
Verfondern, K.; Mueller, D. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer Sicherheitsforschung und Reaktortechnik)

Analytical method of fractional release of fission products from fuel elements of HTTR.
Sawa, K.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai Research Establishment, Oarai, Ibaraki (Japan). Dept. of HTTR Project); Fukuda, K. (Japan Atomic Energy Research Inst., Tokai Research Establishment, Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research); Ichihashi, Y. (Japan Atomic Energy Research Inst., Oarai Research Establishment, Oarai, Ibaraki (Japan). Dept. of JMTR Project)

Release behavior of metallic fission products from fuel for HTTR.
Hayashi, K.; Fukuda, K. (Japan Atomic Energy Research Inst., Tokai Research Establishment, Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research); Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai Research Establishment, Oarai, Ibaraki (Japan). Dept. of HTTR Project)

Behaviour of HTGR coated particles and fuel elements under normal and accident conditions.
Deryugin, A.I.; Koshcheev, K.N.; Momot, G.V.; Khrulyov, A.A.; Chernikov, A.S. (Scientific and Industrial Association ''Lutch'', Podol'sk (USSR))

Diffusion modeling of fission product release during depressurized core conduction cooldown conditions.
Martin, R.C. (Oak Ridge National Lab., TN (United States))

Testing of irradiated spherical fuel elements at HTR MODUL relevant accident conditions.
Schenk, W.; Nabielek, H. (Forschungszentrum Juelich GmbH, Juelich (Germany). Inst. fuer Reaktorwerkstoffe und HTA-Projekt)

The THTR-300 coolant gas activity, an indicator of fuel performance
Roellig, K. (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany))

Preliminary safety assessment of the 450 MWT MHTGR
Dunn, T.D.; Datta, K.; Hoot, C. (General Atomics, San Diego, CA (United States))

Analytical method and result of fission product release from core during a depressurization accident of HTTR
Sawa, K.; Tazawa, Y.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Dept. of HTTR Project); Mikami, H. (Fuji Electric Co., Ltd, Tokyo (Japan). HTR Project Dept.)

Problems of investigation of HTGR fuel elements under loss-of-pressure accident conditions.
Mosevitskij, I.S.; Djakov, A.V. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Inst. Atomnoj Ehnergii)

Fission product retention in TRISO coated UO2 particle fuels subjected to HTR simulated core heating tests
Baldwin, C.A.; Kania, M.J. (Oak Ridge National Lab., TN (United States))

Fission-gas release during hydrolysis of exposed fuel kernels.
Richards, M.B.; Hanson, D.L.; Turner, R.F. (General Atomics, San Diego, CA (United States))

Effect of water vapor on the release of fission gases from UCO in HTGR coated fuel particles.
Myers, B.F. (Oak Ridge National Lab., TN (United States))

HTGR fuel elements operating conditions during accidents with abrupt power raise.
Gorbunov, V.S.; Kiryushin, A.I.; Kuzavkov, N.G.; Sukharev, Yu.P. (Experimental Machine Building Design Bureau, Gorki (USSR))

In-pile corrosion of grade H-451 graphite by steam.
Richards, M.B.; Gillespie, A.G.; Hanson, D.L. (General Atomics, San Diego, CA (United States))