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IWGGCR--24: Uncertainties in physics calculations for gas cooled reactor cores.

Uncertainties in physics calculations for gas cooled reactor cores. Proceedings of a specialist's meeting held in Villigen, Switzerland, 9-11 May 1990

International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors, IWGGCR--24

Abstract

The meeting was attended by 29 participants from Austria, China, France, Germany, Japan, Switzerland, the Union of Soviet Socialist Republics and the United States of America and was subdivided into four technical sessions: Analytical methods, comparison of predictions with results from existing HTGRs, uncertainty evaluations (3 papers). Analytical methods, predictions of performance of future HTGRs, uncertainty evaluations - part 1 (5 papers). Analytical methods, predictions of performance of future HTGRs, uncertainty evaluations - part 2 (6 papers). Critical experiments - planning and results, uncertainty evaluations (5 papers). The participants presented 19 papers on behalf of their countries or organizations.

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Articles

Experimental and theoretical analysis of spent AVR fuels.
Werner, H.; Thomas, F. (Forschungszentrum Juelich GmbH (Germany, F.R.)); Woloch, F.; Reitsamer, G.; Falta, G.; Strigl, A. (Oesterreichisches Forschungszentrum Seibersdorf GmbH (Austria))

French experience in thermohydraulics calculations of gas cooled reactors.
Boutard, F.; Carvallo, G.; Chevalier, G. (CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. d'Etudes Mecaniques et Thermiques)

Progress and problems in modelling HTR core dynamics. The TINTE code tested at AVR power transients
Scherer, W.; Gerwin, H. (Forschungszentrum Juelich GmbH (Germany, F.R.). Inst. fuer Sicherheitsforschung und Reaktortechnik)

Determination of the temperature coefficients and the kinetic parameters for the HTTR safety analysis.
Tokuhara, K. (Fuji Electric Co. Ltd., Tokyo (Japan)); Nakata, T. (Kawasi Heavy Industries Ltd, Tokyo (Japan)); Murata, I.; Yamashita, K.; Shindo, R. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)

Calculational methods of power distribution in the HTTR and verifications
Nakata, T. (Kawasaki Heavy Industries Ltd, Tokyo (Japan)); Tokuhara, K. (Fuji Electric Co. Ltd., Tokyo (Japan)); Murata, I.; Yamashita, K.; Shindo, R. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)

The plant dynamics analysis code ASURA for the High Temperature Engineering Test Reactor (HTTR)
Shimakawa, Y.; Tanji, M. (Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan)); Nakagawa, S.; Fujimoto, N. (Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment)

Physical status of the 10 MW test module.
Luo Jingyu (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology)

Effects of the fuel elements pebble bed structural non-uniformity on the HTGR physical and thermophysical characteristics.
Yevsevev, V.I.; Kiryushin, A.I.; Kuzavkov, N.G.; Mordvintsev, V.M.; Sukharev, Yu.P (Experimenta Machine Building Design Bureau, Gorki (Union of Soviet Socialist Republics))

Uncertainties in calculations of nuclear design code system for the high temperature engineering test reactor (HTTR).
Shindo, R.; Yamashita, K.; Murata, I. (Japan Atomic Energy Research Inst., Orai, Ibaraki (Japan). Dept. of HTTR Project)

Automated differentiation of computer models for sensitivity analysis.
Worley, B.A. (Oak Ridge National Lab., TN (USA))

Impact of different libraries on the performance calculation of a modul-type pebble bed HTR.
Ohlig, U.; Brockmann, H.; Haas, K.A.; Teuchert, E. (Forschungszentrum Juelich GmbH (Germany, F.R.). Inst. fuer Sicherheitsforschung und Reaktortechnik)

Nuclear data related to HTRs
Pelloni, S. (Paul Scherrer Inst. (PSI), Villigen (Switzerland)); Giesser, W. (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany, F.R.))

A review of reactor physics uncertainties and validation requirements for the modular high-temperature gas-cooled reactor.
Baxter, A.M.; Lane, R.K.; Hettergott, E.; Lefler, W. (General Atomics, San Diego, CA (USA)).

Uncertainties in the analysis of water ingress accident for the HTGR cores.
Gorbunov, V.S.; Golovko, V.F.; Glushkov, E.S. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Inst. Atomnoj Ehnergii); Kiryushin, A.I.; Kuzavkov, N.G.; Sukharev, Yu.P. (Experimental Machine Building Design Bureau, Gorki (USSR))

Measurements of temperature coefficient of reactivity of the VHTRC-1 core by the criticality method.
Yasuda, H.; Akino, F.; Yamane, T.; Kaneko, Y. (Japan Atomic Energy Research Inst., Tokai (Japan))

Present status of the proteus HTR experiments
Paul Scherrer Inst. (PSI), Villigen (Switzerland)

Present HTR physics calculational methods at the Paul Scherrer Institute.
Pelloni, S. (Paul Scherrer Inst. (PSI), Villigen (Switzerland))

Uncertainties in HTGR neutron-physical characteristics due to computational errors and technological tolerances.
Glushkov, E.S.; Grebennik, V.N.; Davidenko, V.G.; Kosovskij, V.G.; Smirnov, O.N.; Tsibul'skij, V.F. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Inst. Atomnoj Ehnergii); Sukharev, Yu.P. (Experimental Design Bureau of Machine Building, Gorki (USSR))

Summary of discussion of the future HTGR PROTEUS experiments and other planned experiments.
Scherer, W. (Forschungszentrum Juelich GmbH (Germany, F.R.))