Fukuya Kohji | Institute Of Nuclear Safety System
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概要
関連著者
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Fukuya K
Inst. Of Nuclear Safety System
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Fukuya K
Institute Of Nuclear Safety System
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Fukuya Kohji
Institute Of Nuclear Safety System
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Fujii K
Institute Of Nuclear Safety System
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FUKUYA Koji
Institute of Nuclear Safety System, Inc.
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Fukuya Koji
Institute Of Nuclear Safety System
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FUJII Katsuhiko
Institute of Nuclear Safety System
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TORIMARU Tadahiko
Nippon Nuclear Fuel Development
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NISHIOKA Hiromasa
Institute of Nuclear Safety System
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KITSUNAI Yuji
Nippon Nuclear Fuel Development
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NAKANO Morihito
Institute of Nuclear Safety System
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Nakano Morihito
Institute Of Nuclear Safety System Inc.
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SHIGENAKA Naoto
Power and Industrial Systems R & D Laboratory, Hitachi. Ltd.
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Asano Kyoichi
Power Engineering R&d Center Tokyo Electric Power Co.
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NAKATA Kiyotomo
Hitachi Research Laboratory, Hitachi, Ltd.
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Nakata Kiyotomo
Hitachi Research Laboratory Hitachi Ltd.
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ISOBE Yusuke
Hitachi Works, Hitachi Ltd.
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HASHIMOTO Tsuneyuki
Hitachi Research Laboratory, Hitachi Ltd.
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Isobe Yusuke
Hitachi Works Hitachi Ltd.
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KODAMA Mitsuhiro
Nippon Nuclear Fuel Development Co., Ltd.
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FUKUYA Kohji
Nuclear Engineering Laboratory, Toshiba Corporation
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Kodama Mitsuhiro
Nippon Nuclear Fuel Development Co. Ltd.
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Shigenaka Naoto
Power And Industrial Systems R & D Laboratory Hitachi. Ltd.
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Hashimoto T
Hitachi Research Laboratory Hitachi Ltd.
著作論文
- Evolution of Microstructure and Microchemistry in Cold-worked 316 Stainless Steels under PWR Irradiation
- IASCC Initiation in Highly Irradiated Stainless Steels under Uniaxial Constant Load Conditions
- Effects of Dissolved Hydrogen and Strain Rate on IASCC Behavior in Highly Irradiated Stainless Steels
- Deformation Structure in Highly Irradiated Stainless Steels
- Separation of Microstructural and Microchemical Effects in Irradiation Assisted Stress Corrosion Cracking using Post-irradiation Annealing
- IASCC Susceptibility and Slow Tensile Properties of Highly-irradiated 316 Stainless Steels
- Role of Radiation-Induced Grain Boundary Segregation in Irradiation Assisted Stress Corrosion Cracking
- Segregation Behavior Induced by Various Particle Irradiations in Austenitic Stainless Steels