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IAEA-TECDOC--784: Response of fuel, fuel elements and gas cooled reactor cores under accidental air or water ingress conditions.

Technical committee meeting on response of fuel, fuel elements and gas cooled reactor cores under accidental air or water ingress conditions. Beijing (China). 25-27 Oct 1993

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--784

Abstract

The meeting was convened by the IAEA on the recommendation of the IAEA's International Working Group on Gas Cooled Reactors. It was attended by participants from China, France, Germany, Japan, Netherlands, Switzerland, the Russian Federation, the United Kingdom and the United States of America. The meeting covered the following topics: experimental investigations of the effects of air and water ingress. Predicted response of fuel, graphite and other reactor components. Options for minimizing or mitigating the effects of air or water ingress.

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Articles

China's HTR test module project
Zhong Daxin; Xu Yuanhui; Wu Zongxin (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology)

Fuel irradiation experiments on HFR-K6 and HFR-B1 with intermittent water vapour injections
Nabielek, H. (Forschungszentrum Juelich GmbH (Germany)); Conrad, R. (Joint Research Centre, Petten (Netherlands)); Roellig, K. (ABB Kraftwerke AG, Mannheim (Germany)); Meyers, B.F. (Oak Ridge National Lab., TN (United States))

Experimental study on structural integrity of oxidized support post for HTTR
Ishihara, M.; Iyoku, T.; Shiozawa, S. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment); Miki, T. (Fuji Electric Co. Ltd., Tokyo (Japan)); Takikawa, N. (Kawasaki Heavy Industries Ltd, Tokyo (Japan))

French gas cooled reactor experience with moisture ingress
Bastien, D.; Brie, M. (CEA Centre d'Etudes de Saclay, 91 - Gif-sur-Yvette (France))

Simulation of steam ingress accidents with irradiated fuel elements
Schenk, W.; Nabielek, H. (Forschungszentrum Juelich GmbH (Germany))

Experimental investigations of reactivity effects caused by water ingress in a LEU-LHTR pebble-bed core
Seiler, R.; Chawla, R.; Hager, H.; Mathews, D.; Williams, T. (Paul Scherrer Inst. (PSI), Villigen (Switzerland))

Experimental results of air ingress in heated graphite channels: A summary of American analyses of the Windscale and Chernobyl accidents
Schweitzer, D.G. (Brookhaven National Lab., Upton, NY (United States))

The NACOK experiment on natural convection of air through the core
Froehling, W.; Hohn, H.; Kugeler, M. (Forschungszentrum Juelich GmbH (Germany)); Sun, Y.; Zhang, Z. (Institute of Nuclear Energy Technology, Beijing (China))

Investigation of air ingress accidents under depressurization of the VGM modular reactor primary circuit
Kuzavkov, N.G.; Tonny, S.I.; Shepelev, S.F. (OKBM, Nizhny Novgorod (Russian Federation)); Klyukin, S.M. (Minatom RF, Moscow (Russian Federation)); Zyryanov, S.I. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (Russian Federation). Inst. Atomnoj Ehnergii)

Transient analysis of air ingress from broken pipe into the HTR-10 reactor pressure vessel
Gao Zuying; Li Baoyan; Wang Chunyun; Jiang Zhiqiang (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology)

Evaluating on graphite oxidation during an air ingress accident in HTTR
Iyoku, T.; Maruyama, S.; Ishihara, M.; Shiozawa, S. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment); Ohashi, K.; Okamoto, F.; Hayakawa, H. (Fuji Electric Co. Ltd., Tokyo (Japan))

Scenarios of hypothetical water and air ingress in small modular HTGRs
Scherer, W.; Gerwin, H. (Forschungszentrum Juelich GmbH (Germany))

Thermodynamic analysis of behaviour of HTGR fuel and fission products under accidental air or water ingress conditions
Minato, K.; Fukuda, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)

Transient analysis of water ingress into the HTR-10 high temperature gas cooled test reactor
Gao Zuying; Wang Chunyun (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology)

Evaluation of graphite oxidation during water ingress accidents in HTTR
Maruyama, S.; Saikusa, A.; Ikoku, T.; Kunitomi, K.; Shiozawa, S. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)); Ohashi, K.; Hayakawa, H. (Fuji Electric Co. Ltd., Tokyo (Japan))

Study of reaction: Coated SiC coating on HTGR fuel elements
Tang Chunhe; Guan Jie; Li Ende; Zhang Chun (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology)

The roles of water addition and gas composition in AGR accident management
Dawson, J.T. (Nuclear Electric plc, Berkeley (United Kingdom)); Smith, P.N. (AEA Technology, Winfrith (United Kingdom))

Study of the method to improve the corrosion resistance of the matrix materials of spherical fuel elements in HTGR
Zhang Shichao; Qiu Xueliang; Ma Changwen (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology)

Ceramic coatings for HTR graphitic structures
Hurtado, A.M. (Aachen Univ., Aachen (Germany). Inst. of Reactor Safety and Technology); Schroeder, B.; Gottaut, H. (Forschungszentrum Juelich GmbH (Germany))