Deformation Structure in Highly Irradiated Stainless Steels
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概要
- 論文の詳細を見る
Surface steps and deformation microstructure in cold-worked SUS316 stainless steels irradiated to 4 and 35 dpa (displacements per atom) were examined after being deformed by uniaxial tensile stress at 320°C at a slow or fast strain rate. Dislocation channeling was the predominant mode of deformation near the surface at the slow strain rate. Twinning was dominant at the fast strain rate whereas twinning and nanotwin formation occurred in the locally stressed area at the slow strain rate. Deformation heterogeneity measured using the spacing of coarse surface steps induced by dislocation channels increased with increasing dose from 4 to 35 dpa. Grain boundary separation occurred when dislocation pileups and high normal stress on the grain boundary plane coexisted, which likely was a precursor of intergranular cracking without any environmental factor.
- 社団法人 日本原子力学会の論文
- 2008-04-25
著者
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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 Koji
Institute Of Nuclear Safety System
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NISHIOKA Hiromasa
Institute of Nuclear Safety System
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FUJII Katsuhiko
Institute of Nuclear Safety System
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KITSUNAI Yuji
Nippon Nuclear Fuel Development
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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
関連論文
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- Angular Distribution of Slip Steps by Three-Dimensional Polycrystalline Model for Stainless Steel
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- 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
- Segregation Behavior Induced by Various Particle Irradiations in Austenitic Stainless Steels
- Calculation of Gamma Induced Displacement Cross-sections of Iron Considering Positron Contribution and Using Standard Damage Model
- 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℃
- Calculation of Gamma Induced Displacement Cross-sections of Iron Considering Positron Contribution and Using Standard Damage Model
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels