FUJII Katsuhiko | Institute of Nuclear Safety System
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概要
関連著者
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FUJII Katsuhiko
Institute of Nuclear Safety System
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Fukuya Koji
Institute Of Nuclear Safety System
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FUKUYA Koji
Institute of Nuclear Safety System, Inc.
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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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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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笠田 竜太
京都大学エネルギー理工学研究所
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福谷 耕司
株式会社原子力安全システム研究所技術システム研究所
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Kasada Ryuta
Institute Of Advanced Energy Kyoto University
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NAKATA Hayato
Institute of Nuclear Technology, Institute of Nuclear Safety System Incorporated
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Kimura Akihiko
Institute Of Advanced Energy Kyoto University
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Fujii Katsuhiko
Institute Of Nuclear Safety System Inc.
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ARIOKA Koji
Institute of Nuclear Safety System, Inc.
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木村 晃彦
京都大学エネルギー理工学研究所
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Kasada Ryuta
Institute of Advanced Energy, Kyoto University
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Kimura Akihiko
Institute of Advanced Energy, Kyoto University
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笠田 竜太
京都大学 エネルギー理工学研究所
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Fukuya Koji
Institute Of Nuclear Technology Institute Of Nuclear Safety System Incorporated
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Arioka Koji
Institute Of Nuclear Safety System Inc.
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Terachi Takumi
Institute Of Nuclear Safety System Inc.
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中田 早人
近畿大 原子力研
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
- A Multicomponent Model of Radiation-induced Segregation for Commercial Stainless Steels
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Development of Micro Tensile Testing Method in an FIB System for Evaluating Grain Boundary Strength
- Microstructural Characterization of SCC Crack Tip and Oxide Film for SUS 316 Stainless Steel in Simulated PWR Primary Water at 320℃
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels