A five-year research project has been initiated in 2005 to develop a code based on the MPS (Moving Particle Semi-implicit) method for detailed analysis of specific phenomena in core disruptive accidents (CDAs) of sodium-cooled fast reactors (SFRs). The code is named COMPASS (Computer Code with Moving Particle Semi-implicit for Reactor Safety Analysis). The specific phenomena include 1) fuel pin failure and disruption, 2) molten pool boiling, 3) melt freezing and blockage formation, 4) duct wall failure, 5) low-energy disruptive core motion, 6) debris-bed coolability, and 7) metal-fuel pin failure. Validation study of COMPASS is progressing for these key phenomena. In this paper, recent COMPASS results of detailed analyses for the several specific phenomena are summarized. Simulations of GEYSER and THEFIS experiments were performed for dispersion and freezing behaviors of molten materials in narrow flow channels. In particular, the latter experiment using melt-solid mixture is also related to fundamental behavior of low energy disruptive core. CABRI-TPA2 experiment was simulated for boiling behavior of molten core pool. Expected mechanism of heat transfer between molten fuel and steel mixture was reproduced by the simulation. Analyses of structural dynamics using elastoplastic mechanics and failure criteria were performed for SCARABEE BE+3 and CABRI E7 experiments. These two analyses are especially focused on thermal and mechanical failure of steel duct wall and fuel pin, respectively. The present results demonstrate COMPASS will be useful to understand and clarify the specific phenomena of CDAs in SFRs in details.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
Detailed Analyses of Specific Phenomena in Core Disruptive Accidents of Sodium-Cooled Fast Reactors by the COMPASS Code
Koji Morita,
Koji Morita
Kyushu University, Fukuoka, Japan
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Shuai Zhang,
Shuai Zhang
Kyushu University, Fukuoka , Japan
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Tatsumi Arima,
Tatsumi Arima
Kyushu University, Fukuoka, Japan
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Seiichi Koshizuka,
Seiichi Koshizuka
The University of Tokyo, Tokyo, Japan
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Yoshiharu Tobita,
Yoshiharu Tobita
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
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Hidemasa Yamano,
Hidemasa Yamano
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
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Takahiro Ito,
Takahiro Ito
Toyohashi University of Technology, Toyohashi, Aichi, Japan
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Noriyuki Shirakawa,
Noriyuki Shirakawa
The Institute of Applied Energy, Tokyo, Japan
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Fusao Inoue,
Fusao Inoue
The Institute of Applied Energy, Tokyo, Japan
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Hiroaki Yugo,
Hiroaki Yugo
The Institute of Applied Energy, Tokyo, Japan
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Masanori Naitoh,
Masanori Naitoh
The Institute of Applied Energy, Tokyo, Japan
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Hidetoshi Okada,
Hidetoshi Okada
The Institute of Applied Energy, Tokyo, Japan
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Yuichi Yamamoto,
Yuichi Yamamoto
Japan Systems Corporation, Kawasaki, Japan
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Masashi Himi,
Masashi Himi
Japan Systems Corporation, Kawasaki, Japan
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Etsujo Hirano,
Etsujo Hirano
Japan Systems Corporation, Kawasaki, Japan
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Sensuke Shimizu,
Sensuke Shimizu
Japan Systems Corporation, Kawasaki, Japan
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Masaya Oue
Masaya Oue
Japan Systems Corporation, Kawasaki, Japan
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Koji Morita
Kyushu University, Fukuoka, Japan
Shuai Zhang
Kyushu University, Fukuoka , Japan
Tatsumi Arima
Kyushu University, Fukuoka, Japan
Seiichi Koshizuka
The University of Tokyo, Tokyo, Japan
Yoshiharu Tobita
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
Hidemasa Yamano
Japan Atomic Energy Agency, O-arai, Ibaraki, Japan
Takahiro Ito
Toyohashi University of Technology, Toyohashi, Aichi, Japan
Noriyuki Shirakawa
The Institute of Applied Energy, Tokyo, Japan
Fusao Inoue
The Institute of Applied Energy, Tokyo, Japan
Hiroaki Yugo
The Institute of Applied Energy, Tokyo, Japan
Masanori Naitoh
The Institute of Applied Energy, Tokyo, Japan
Hidetoshi Okada
The Institute of Applied Energy, Tokyo, Japan
Yuichi Yamamoto
Japan Systems Corporation, Kawasaki, Japan
Masashi Himi
Japan Systems Corporation, Kawasaki, Japan
Etsujo Hirano
Japan Systems Corporation, Kawasaki, Japan
Sensuke Shimizu
Japan Systems Corporation, Kawasaki, Japan
Masaya Oue
Japan Systems Corporation, Kawasaki, Japan
Paper No:
ICONE18-29886, pp. 855-863; 9 pages
Published Online:
April 8, 2011
Citation
Morita, K, Zhang, S, Arima, T, Koshizuka, S, Tobita, Y, Yamano, H, Ito, T, Shirakawa, N, Inoue, F, Yugo, H, Naitoh, M, Okada, H, Yamamoto, Y, Himi, M, Hirano, E, Shimizu, S, & Oue, M. "Detailed Analyses of Specific Phenomena in Core Disruptive Accidents of Sodium-Cooled Fast Reactors by the COMPASS Code." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 855-863. ASME. https://doi.org/10.1115/ICONE18-29886
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