Narabayashi Tadashi | Graduate School Of Engineering Hokkaido University
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概要
関連著者
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Narabayashi Tadashi
Graduate School Of Engineering Hokkaido University
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Tsuji Masashi
Graduate School of Engineering, Hokkaido University
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Tsuji Masashi
Division Of Energy And Environmental System Graduate School Of Engineering Hokkaido University
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TSUJI Masashi
Hokkaido University
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Tsuji Masashi
Graduate School Of Engineering Hokkaido University
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Chiba Go
Advanced Nuclear System Research And Development Directorate Japan Atomic Energy Agency
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Shimazu Yoichiro
Research Institute Of Reactor Engineering University Of Fukui
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CHIBA Go
Hokkaido University
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TSUJI Masashi
Division of Molecular Chemistry, Graduate School of Engineering, Hokkaido University
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Sugiyama Ken-ichiro
Hokkaido Univ.
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NARABAYASHI Tadashi
Hokkaido University
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SHIMAZU Yoichiro
Division of Energy and Environmental System, Graduate School of Engineering, Hokkaido University
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NARABAYASHI Tadashi
Division of Energy and Environmental System, Graduate School of Engineering, Hokkaido University
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OHOKA Yasunori
Nuclear Fuel Industries, Ltd.
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YAMASAKI Masatoshi
Nuclear Fuel Industries, Ltd.
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HANAYAMA Yasushi
Nuclear Fuel Industries, Ltd.
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Ohoka Yasunori
Nuclear Fuel Industries Ltd.
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Hanayama Yasushi
Nuclear Fuel Industries Ltd.
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Yamasaki Masatoshi
Nuclear Fuel Industries Ltd.
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Yamamoto Akio
Graduate School Of Energy Science Kyoto University
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Chiba Go
Graduate School Of Engineering Hokkaido University
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MORI Michitsugu
Research & Development Center, The Tokyo Electric Power Company, Incorporated
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OHMORI Shuichi
Research & Development Center, The Tokyo Electric Power Company, Incorporated
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OHMORI Shuichi
Research & Development Center, The Tokyo Electric Power Company, Incorporated
著作論文
- Scale Model Test and Transient Analysis of Steam Injector Driven Passive Core Injection System for Innovative-Simplified Nuclear Power Plant
- Estimation of the Doppler Coefficient from a Lower Power Transient Observed in a Zero-Power Reactor Physics Test of a PWR (I) : Methodology
- Examination of Actual Neutron Count Rate Data during a Control Rod Drop Testing for Estimation of Control Rod Worth in PWRs
- JENDL-4.0 Benchmarking for Effective Delayed Neutron Fraction of Fast Neutron Systems
- Efficient fission neutron spectrum matrix representation by singular value decomposition technique