NAITOH Masanori | Nuclear Power Engineering Corporation

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• 同名の論文著者
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関連著者

• NAITOH Masanori

  Nuclear Power Engineering Corporation

• Naitoh Masanori

  Advanced Simulation Systems Department Nuclear Power Engineering Corporation Fujita Kanko

• UCHIDA Shunsuke

  The Institute of Applied Energy

• NAITOH Masanori

  The Institute of Applied Energy

• KOSHIZUKA Seiichi

  University of Tokyo

• Uchida S

  Japan Atomic Energy Agency

• Uchida S

  Tohoku Univ. Sendai

• Araki Kazuhiro

  Fuji Research Institute Corporation

• HIRANUMA Naoki

  Tokyo Electric Power Co.

• UCHIDA Shunsuke

  Nuclear Power Engineering Corporation

• Ikeda Takashi

  Advanced Simulation Systems Department, Nuclear Power Engineering Corporation

• Vierow K

  Advanced Simulation Systems Department Nuclear Power Engineering Corporation

• Vierow Karen

  Nuclear Power Engineering Corporation

• Tomio Okawa

  Department Of Mechanical Engineering Osaka University

• Okawa Tomio

  Department Of Mechanophysics Engineering Osaka University

• Uchida Shunsuke

  Department Of Quantum Science And Energy Engineering Graduate School Of Engineering Tohoku Universit

• Uchida Shunsuke

  Power And Industrial Systems R&d Division Hitachi Ltd.

• Uchida Shunsuke

  Energy Research Laboratory Hitachi Ltd.

• Naitoh Masanori

  Advanced Simulation Systems Department Nuclear Power Engineering Corporation

• NAGANO Katsuhiro

  Fuji Research Institute Corporation

• Ohshima Iwao

  Nuclear And Industrial Safety Agency Ministry Of Economy Trade And Industry

• Kataoka I

  Department Of Mechanical Engineering Osaka University

• Kataoka I

  Department Of Mechanophysics Engineering Osaka University

• Kasahara Fumio

  Nuclear Power Engineering Corporation

• Koshizuka Seiichi

  The University Of Tokyo Department Of Systems Innovation

• UEHARA Yasushi

  The Institute of Applied Energy

• OKADA Hidetoshi

  The Institute of Applied Energy

• SUGINO Wataru

  Japan Atomic Power Co.

• Ninokata Hisashi

  Tokyo Inst. Of Technol.

• UEHARA Yasushi

  Nuclear Power Engineering Corporation

• OKADA Hidetoshi

  Nuclear Power Engineering Corporation

• DOSAKI Koji

  Japan Atomic Power Co.

• NISHIDA Koji

  Hitachi, Ltd.

• AKIYAMA Minoru

  Mizuho Information & Research Institute, Inc.

• SAITOH Hiroaki

  ITOCHU Techno-Solutions, Corp.

• OKAWA Tomio

  Department of Mechanophysics Engineering, Osaka University

• KATAOKA Isao

  Department of Mechanophysics Engineering, Osaka University

• Ninokata Hisashi

  Res. Lab. For Nuclear Reactors Tokyo Inst. Of Technol.

• NAITOH Masanori

  Advanced Simulation Systems Department, Nuclear Power Engineering Corporation

• Saitoh Hiroaki

  Itochu Techno-solutions Corp.

• Okawa Tomio

  Osaka University

• Okawa Tomio

  Osaka Univ.

• Ujita H

  Nuclear Power Engineering Corp. Tokyo

• Ujita Hiroshi

  Advanced Simulation Systems Department Nuclear Power Engineering Corporation

• KUBOTA Ryoko

  Fuji Research Institute Corporation

• MITSUHASHI Toshiharu

  Fuji Research Institute Corporation

• Kataoka Isao

  Department Of Mechanical Engineering Graduate School Of Engineering Osaka University

• KIM Saeyun

  Osaka University

• KATAOKA Isao

  Osaka University

• NISHIDA Koji

  Power & Industrial Systems R&D Laboratory, Hitachi, Ltd.

• Akiyama Minoru

  Mizuho Information & Research Institute Inc.

• Nishida Koji

  Hitachi Ltd.

• Nishida Koji

  Power & Industrial Systems R&d Laboratory Hitachi Ltd.

• Okawa Tomio

  Department of Mechanical Engineering, Osaka University

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著作論文

• Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (II) : Evaluation of Corrosive Conditions in PWR Secondary Cooling System
• Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (I) : Major Targets and Development Strategies of the Evaluation Methods
• Development of the VESUVIUS Code for Steam Explosion Analysis : Part 2 : Verification of Jet Breakup Modeling
• Development of the VESUVIUS Code for Steam Explosion Analysis : Part 1 : Molten Jet Breakup Modeling
• Prediction of Dryout Heat Flux Using Film Flow Model
• Critical Power Analysis with Mechanistic Models for Nuclear Fuel Bundles,(I) Models and Verifications for Boiling Water Reactor Application
• Analysis on Pipe Rupture of Steam Condensation Line at Hamaoka-1, (II) Hydrogen Combustion and Pipe Deformation
• Analysis on Pipe Rupture of Steam Condensing Line at Hamaoka-1, (I) Accumulation of Non-condensable Gas in a Pipe
• Severe Accident Analysis Code SAMPSON Improvement for IMPACT Project(Special Issue on International Conference on Power and Energy System)

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