Shirakawa N | Power & Industrial Systems Reserch & Development Center Toshiba Corporation
スポンサーリンク
概要
関連著者
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Shirakawa N
Power & Industrial Systems Reserch & Development Center Toshiba Corporation
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Shirakawa Noriyuki
Institute Of Environmental Systems Faculty Of Engineering Kyushu University
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Shirakawa Noriyuki
Toshiba Power & Industrial Systems R&d Center
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Horie H
Toshiba Power & Industrial Systems R&d Center
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SHIRAKAWA Noriyuki
TOSHIBA Power & Industrial Systems R&D Center
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YAMAMOTO Yuichi
Toshiba Advanced Systems Corporation
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Yamamoto Yuichi
Toshiba It-solutions Corporation
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IKEDA Takashi
Nuclear Power Engineering Corporation
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HORIE Hideki
TOSHIBA Power & Industrial Systems R&D Center
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Shirakawa Noriyuki
Nuclear Engineering Laboratory Toshiba Corporation
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KATSURAGI Kazuyuki
Mitsubishi Heavy Industries, Ltd.
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TSUNOYAMA Shigeaki
University of Aizu, University-Business Innovation Center
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Katsuragi Kazuyuki
Mitsubishi Heavy Industries Ltd.
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Tsunoyama Shigeaki
University Of Aizu University-business Innovation Center
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Ikeda Takashi
Nuclear Power Engineering Corporation Toranomon
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SHIRAKAWA Noriyuki
Power & Industrial Systems R&D Center, Toshiba Corporation
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Nakahara Katsuhiko
Toshiba Corporation
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HORIE Hideki
Power & Industrial Systems Research & Development Center, Toshiba Corporation
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Yamagishi Makoto
Reactor Safety Engineering Department, Mitsubishi Heavy Industries, Ltd.
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SATOH Nobuhide
Nuclear Power Engineering Corporation (NUPEC)
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Horie Hideki
Power & Industrial Systems Reserch & Development Center Toshiba Corporation
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Ujita H
Nuclear Power Engineering Corp. Tokyo
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Yamagishi Makoto
Mitsubishi Heavy Industries Ltd.
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Yamagishi Makoto
Reactor Control & Safety Engineering Department Mitsubishi Heavy Industries Ltd.
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Terada Masafumi
Nuclear Power Engineering Corporation Toranomon
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Katsuragi Kazuyuki
Reactor Safety Engineering Department Mitsubishi Heavy Industries Ltd.
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MORITA Koji
Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University
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ITO Takahiro
Department of Nuclear Engineering, Nagoya University
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NAKAHARA Katsuhiko
Power and Industrial Systems R&D Center, Toshiba Corporation
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Nakahara Katsuhiko
Power And Industrial Systems R&d Center Toshiba Corp.
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YAMAGUCHI Akira
O-arai Engineering Center, Japan Nuclear Cycle Development Institute
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TSUNOYAMA Shigeaki
TOSHIBA Isogo Engineering Center
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Morita Koji
Department Of Applied Quantum Physics And Nuclear Engineering Kyushu University
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MORITA Koji
National Institute for Materials Science
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ZHANG Shuai
Department of Applied Quantum Physics and Nuclear Engineering, Graduate School of Engineering, Kyush
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MORITA Koji
Institute of Environmental Systems, Faculty of Engineering, Kyushu University
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Terada Masafumi
Advanced Simulation Systems Department, Nuclear Power Engineering Corporation
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Ikeda Takashi
Advanced Simulation Systems Department, Nuclear Power Engineering Corporation
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Karasawa Hidetoshi
Nuclear Systems Division, Hitachi Ltd.
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Satou Kenichi
Nuclear Systems Division, Hitachi Ltd.
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Matsumoto Tomoyuki
Nuclear Systems Division, Hitachi Ltd.
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Yamagishi Makoto
Mitsubishi Heavy Industries, Ltd.
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Terada Masafumi
Nuclear Power Engineering Corporation
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Katsuragi Kazuyuki
Reactor Safety Engineering Department, Mitsubishi Heavy Industries, Ltd.
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TSUNOYAMA Shigeaki
AITEL Corporation
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OKANO Yasushi
O-arai Engineering Center, Japan Nuclear Cycle Development Institute
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UJITA Hiroshi
Nuclear Power Engineering Corporation (NUPEC)
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MIYAGI Kazumi
Nuclear Engineering Laboratory, Toshiba Corporation
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HORIE Hideki
Nuclear Engineering Laboratory, Toshiba Corporation
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NAKAHARA Katsuhiko
Nuclear Engineering Laboratory, Toshiba Corporation
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SASAKAWA Hiroshi
Nuclear Engineering Laboratory, Toshiba Corporation
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UJITA Hiroshi
Advanced Simulation Systems Department, Nuclear Power Engineering Corporation
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SATOH Nobuhide
Advanced Simulation Systems Department, Nuclear Power Engineering Corporation
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NAITOH Masanori
Advanced Simulation Systems Department, Nuclear Power Engineering Corporation
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HIDAKA Masataka
Power & Industrial Systems R&D Laboratory, Hitachi, Ltd.
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KARASAWA Hidetoshi
Hitachi Ltd.
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Okano Yasushi
O-arai Engineering Center Japan Nuclear Cycle Development Institute
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Naitoh Masanori
Advanced Simulation Systems Department Nuclear Power Engineering Corporation
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Matsumoto Tomoyuki
Nuclear Systems Division Hitachi Ltd.
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Zhang Shuai
Department Of Applied Quantum Physics And Nuclear Engineering Graduate School Of Engineering Kyushu
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Satou Kenichi
Nuclear Systems Division Hitachi Ltd.
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Ujita Hiroshi
Advanced Simulation Systems Department Nuclear Power Engineering Corporation
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Miyagi Kazumi
Nuclear Engineering Laboratory Toshiba Corporation
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Hidaka Masataka
Power & Industrial Systems R&d Laboratory Hitachi Ltd.
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Sasakawa Hiroshi
Nuclear Engineering Laboratory Toshiba Corporation
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Morita Koji
Institute Of Environmental Systems Faculty Of Engineering Kyushu University
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Morita Koji
Department Of Materials Science And Technology Graduate School Of Engineering Sciences Kyushu Univer
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Ito Takahiro
Department Of Aeronautics And Astronautics University Of Tokyo
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Yamaguchi Akira
O-arai Engineering Center Japan Nuclear Cycle Development Institute
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NAKAHARA Katsuhiko
Nuclear Engineering Laboratory, Toshiba Corp.
著作論文
- Analysis of the Void Distribution in a Circular Tube with the Two-Fluid Particle Interaction Method
- Simulation of the Rayleigh-Taylor Instability with the MPS Method
- Analysis of International Standard Problem No. 45, QUENCH06 Test as FZK by Detailed Severe Accidents Analysis Code, IMPACT/SAMPSON
- Analysis of Subcooled Boiling with the Two-Fluid Particle Interaction Method
- ICONE11-36423 Analysis of Fission Product Behaviors in the Phebus-FPT1 Test with IMPACT/SAMPSON Code
- ICONE11-36297 ANALYSIS OF THE THERMAL HYDRAULICS AND CORE DEGRADATION BEHAVIOR IN THE PHEBUS-FPT1 TEST TRAIN WITH IMPACT/SAMPSON CODE
- Analysis of Flows around a BWR Spacer by the Two-Fluid Particle Interaction Method
- Analysis of Jet Flows with the Two-Fluid Particle Interaction Method
- Development of Molten Core Relocation Analysis Module MCRA in the Severe Accident Analysis Code SAMPSON
- Development of Severe Accident Analysis Code SAMPSON in IMPACT Project
- Analysis of International Standard Problem No. 45, QUENCH06 Test as FZK by Detailed Severe Accidents Analysis Code, IMPACT/SAMPSON