HTGR Knowledge Base

IAEA-TECDOC--757: Decay heat removal and heat transfer under normal and accident conditions in gas cooled reactors.

Specialists meeting on decay heat removal and heat transfer under normal and accident conditions in gas cooled reactors. Juelich (Germany). 6-8 Jul 1992

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--757

Abstract

The meeting was convened by the International Atomic Energy Agency on the recommendation of the IAEA's International Working Group on Gas Cooled Reactors. It was attended by participants from China, France, Germany, Japan, Poland, the Russian Federation, Switzerland, the United Kingdom and the United States of America. The meeting was chaired by Prof. Dr. K. Kugeler and Prof. Dr. E. Hicken, Directors of the Institute for Safety Research Technology of the KFA Research Center, and covered the following: Design and licensing requirements for gas cooled reactors. Concepts for decay heat removal in modern gas cooled reactors. Analytical methods for predictions of thermal response, accuracy of predictions. Experimental data for validation of predictive methods - operational experience from gas cooled reactors and experimental data from test facilities.

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Articles

Principles of decay heat removal in reactor technology - Present status and future prospects
Kugeler, K. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer Sicherheitsforschung und Reaktortechnik)

Safety criteria and provisions for the evacuation of residual heat from graphite gas cooled reactors
Lheureux, R. (SPT, Division Calculus Nucleaires, Paris - La Defense (France)); Aguilera, A. (Centrale Nucleaire de Saint-Laurent A, La Ferte-Saint-Cyr (France))

Bases for the MHTGR source term and containment concepts
Williams, P.M. (USDOE, Washington, DC (United States))

The ultimate safety of the HTR-Module during hypothetical accidents
Lohnert, G.H. (Siemens AG Unternehmensbereich KWU, Bergisch Gladbach (Germany). Bereich Energieerzeugung, Nukleare Entsorgung und Entwicklungsprojekte)

Distribution of the decay heat in various module HTRs and influence on peak fuel temperatures
Teuchert, E.; Haas, K.A.; Heek, A. van (Forschungszentrum Juelich GmbH (Germany)); Kasten, P.R. (Tennessee Univ., Knoxville, TN (United States))

Afterheat removal for HTR-10 test module under accident conditions
Gao Zuying; He Shuyan; Zhang Min (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology)

Flow schemes and design features of HTGR residual heat removal systems
Golovko, V.F.; Kiryuschin, A.I.; Kuzavkov, N.G. (OKBM, Nizhny Novgorod (Russian Federation))

Passive decay and residual heat removal in the MHTGR
Dilling, D.A.; Ghose, S.K.; Berkoe, J.M. (Bechtel National, Inc., San Francisco, CA (United States)); Caspersson, S.A. (ABB/Combustion Engineering, Inc., Windsor, CT (United States)); Bramblett, G.C. (General Atomics, San Diego, CA (United States))

Impact of increasing MHTGR power on passive heat removal
Dunn, T.D.; Schwartz, A.A.; Silady, F.A. (General Atomics, San Diego, CA (United States))

Trends in safety criteria for future reactor plants
Hicken, E. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer Sicherheitsforschung und Reaktortechnik)

Analytical and experimental investigations of the passive heat transport in HTRs under severe accident conditions
Rehm, W.; Barthels, H.; Jahn, W. (Forschungszentrum Juelich GmbH (Germany)); Cleveland, J. (Oak Ridge National Lab., TN (United States)); Ishihara, M. (Japan Atomic Energy Research Inst., Ibaraki (Japan))

Presentation of decay heat removal computer codes used for gas cooled reactors
Carvallo, G.; Dobremelle, M.; Mejane, A. (CEA Centre d'Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie)

Modeling and analysis of heat transfer from the MHTGR core through a steel reactor vessel to the reactor cavity cooling system
Dilling, D.A.; Berkoe, J.M.; Ghose, S.K. (Bechtel National, Inc., San Franciso, CA (United States)); Dunn, T.D. (General Atomics, San Diego, CA (United States)); Caspersson, S.A. (ABB/Combustion Engineering, Inc., Windsor, CT (United States))

Analysis of afterheat removal from modular HTGRs during accidents, and a concept for use of spherical fuel elements in LWRs
Mosevitskij, I.S.; Goltsev, A.O.; Mikhailov, P.V.; Tsibulskij, V.F.; Davidenko, V.D.; Popov, V.S.; Udyanskij, Yu.N. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (Russian Federation). Inst. Atomnoj Ehnergii)

Heat transfer in the upper part of the HTTR pressure vessel during loss of forced cooling
Shiina, Y.; Hishida, M. (Japan Atomic Energy Research Inst., Ibaraki (Japan))

Development of an inactive heat removal system for high temperature reactors
Kugeler, K. (Rheinisch-Westfaelische Technische Hoschschule, Aachen (Germany)); Sappok, M.; Beine, B. (Siempelkamp Giesserei GmbH und Co., Krefeld (Germany)); Wolf, L. (Battelle-Institut e.V., Frankfurt am Main (Germany))

Passive heat removal experiments for an advanced HTR-module reactor pressure vessel and cavity design
Wolf, L.; Kneer, A.; Schulz, R.; Giannikos, A.; Haefner, W. (Battelle-Institut e.V., Frankfurt am Main (Germany))

Test apparatus of cooling panel system for MHTGR
Takada, S.; Suzuki, K.; Inagaki, Y.; Miyamoto, Y. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of High Temperature Engineering)

SANA experiments related to self-operating removal of decay heat
Niessen, H.F.; Lange, M.G. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer Sicherheitsforschung und Reaktortechnik)