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Journal of Nuclear Science and Technology Volume 37, 2000 - Issue 3
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Original Articles

Development of Molten Core Relocation Analysis Module MCRA in the Severe Accident Analysis Code SAMPSON

Nobuhide SATOH Nuclear Power Engineering Corporation (NUPEC), Toranomon, Minato-ku, Tokyo, 105-0001
,
Hiroshi UJITA Nuclear Power Engineering Corporation (NUPEC), Toranomon, Minato-ku, Tokyo, 105-0001
,
Kazumi MIYAGI Nuclear Engineering Laboratory, Toshiba Corporation, Ukishima-cho, Kawasaki-ku, Kawasaki, 210-0862
,
Noriyuki SHIRAKAWA Nuclear Engineering Laboratory, Toshiba Corporation, Ukishima-cho, Kawasaki-ku, Kawasaki, 210-0862
,
Hideki HORIE Nuclear Engineering Laboratory, Toshiba Corporation, Ukishima-cho, Kawasaki-ku, Kawasaki, 210-0862
,
Katsuhiko NAKAHARA Nuclear Engineering Laboratory, Toshiba Corporation, Ukishima-cho, Kawasaki-ku, Kawasaki, 210-0862
&
Hiroshi SASAKAWA Nuclear Engineering Laboratory, Toshiba Corporation, Ukishima-cho, Kawasaki-ku, Kawasaki, 210-0862
 show all
Pages 225-236 | Received 21 Oct 1998, Published online: 07 Feb 2012

Citations (18)

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Isao Kataoka. (2013) Review of thermal-hydraulic researches in severe accidents in light water reactors. Journal of Nuclear Science and Technology 50:1, pages 1-14.
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Takashi IKEDA, Kazuyuki KATSURAGI & Noriyuki SHIRAKAWA. (2003) Analysis of International Standard Problem No. 45, QUENCH06 Test at FZK by Detailed Severe Accidents Analysis Code, IMPACT/SAMPSON. Journal of Nuclear Science and Technology 40:4, pages 246-255.
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Masataka HIDAKA, Nobuhide SATO & Hiroshi UJITA. (2002) Verification for Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code ‘SAMPSON’, (II). Journal of Nuclear Science and Technology 39:5, pages 520-530.
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Masataka HIDAKA & Hiroshi UJITA. (2001) Verification for Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code ‘SAMPSON’, (I). Journal of Nuclear Science and Technology 38:9, pages 745-756.
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Hiroshi UJITA & Masataka HIDAKA. (2001) Model Verification of the Debris Coolability Analysis Module in the Severe Accident Analysis Code ‘SAMPSON’. Journal of Nuclear Science and Technology 38:4, pages 229-241.
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Hiroshi UJITA, Masataka HIDAKA, Akira SUSUKI & Naoyuki ISHIDA. (1999) Development of Debris Coolability Analysis Module in Severe Accident Analysis Code SAMPSON for IMPACT Project. Journal of Nuclear Science and Technology 36:10, pages 940-951.
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Articles from other publishers (12)

S. N. Ryzhov, E. V. Bogdanova, A. A. Ryzhkov, P. A. Pugachev, G. V. Tikhomirov, M. Yu. Ternovykh & T. B. Aleeva. (2023) Analysis of Methods and Technologies for Assessing the Composition of the Corium Formed as a Result of the Accident at the Fukushima Daiichi NPP. Physics of Atomic Nuclei 85:S2, pages S90-S102.
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S. N. Ryzhov, E. V. Bogdanova, A. A. Ryzhkov, P. A. Pugachev, G. V. Tikhomirov, M. Yu. Ternovykh & T. B. Aleeva. (2022) Analysis of Methods and Technologies for Composition Assessing of Corium Formed as a Result of the Fukushima Daiichi NPP Accident. Global Nuclear Safety:3, pages 5-21.
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Daniel Dupleac, Roxana-Mihaela Nistor-Vlad, Chris Allison, Judith Hohorst & Marina Perez-Ferragut. (2021) Development of the ASYST VER 3.x LWR/HPWR Best Estimate Integral Code. Development of the ASYST VER 3.x LWR/HPWR Best Estimate Integral Code.
Marco Pellegrini. 2021. Nuclear Power Plant Design and Analysis Codes. Nuclear Power Plant Design and Analysis Codes 397 416 .
Susumu Yamashita, Takuya Ina, Yasuhiro Idomura & Hiroyuki Yoshida. (2017) A numerical simulation method for molten material behavior in nuclear reactors. Nuclear Engineering and Design 322, pages 301-312.
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Alessandro Franci, Eugenio Oñate, Josep Maria Carbonell & Michele Chiumenti. (2017) PFEM formulation for thermo-coupled FSI analysis. Application to nuclear core melt accident. Computer Methods in Applied Mechanics and Engineering 325, pages 711-732.
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Tsuyoshi Okawa & Tetsuo Nakajima. (2017) Modeling and verification of three-dimensional simulation for BWR in-vessel core degradation. Annals of Nuclear Energy 101, pages 182-195.
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Susumu YAMASHITA, Kazuyuki TOKUSHIMA, Masaki KURATA & Hiroyuki YOSHIDA. (2017) Development of numerical simulation method for melt relocation behavior in nuclear reactors: validation and applicability for actual core structures. Mechanical Engineering Journal 4:3, pages 16-00567-16-00567.
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M. Pellegrini, L. Bautista Gomez, N. Maruyama, M. Naitoh, S. Matsuoka & F. Cappello. (2014) SAMPSON Parallel Computation for Sensitivity Analysis of TEPCO's Fukushima Daiichi Nuclear Power Plant Accident. SAMPSON Parallel Computation for Sensitivity Analysis of TEPCO's Fukushima Daiichi Nuclear Power Plant Accident.
Masataka HIDAKA, Nobuhide SATO & Hiroshi UJITA. (2002) Verification for Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code 'SAMPSON'. (II).. Journal of Nuclear Science and Technology 39:5, pages 520-530.
Crossref
Hiroshi UJITA, Takashi IKEDA & Masanori NAITOH. (2002) Severe Accident Analysis Code SAMPSON Improvement for IMPACT Project.. JSME International Journal Series B 45:3, pages 607-614.
Crossref
Masataka HIDAKA & Hiroshi UJITA. (2001) Verification for Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code 'SAMPSON', (I).. Journal of Nuclear Science and Technology 38:9, pages 745-756.
Crossref

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