Effects of Dissolved Hydrogen and Strain Rate on IASCC Behavior in Highly Irradiated Stainless Steels
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概要
- 論文の詳細を見る
IASCC behavior in cold-worked SUS316 stainless steels irradiated to 35 dpa was examined using slow strain rate tensile testing at a strain rate of 6.7×10−8/s in 320°C simulated PWR primary water while varying the dissolved hydrogen (DH) concentration from 0 to 2.8 ppm. The results were compared with those previously obtained at a higher strain rate using specimens of different sizes and with those of the previous interrupted experiment. The initiation and propagation of IASCC enhanced with increasing DH concentration and lower strain rate. The IASCC initiation stress decreased to almost half of the yield strength at high DH. Accompanying slow tensile tests in an argon gas environment showed that a lower strain rate did not change in the initiation stress that exceeded the yield strength, but enhanced the propagation of intergranular cracking.
- 社団法人 日本原子力学会の論文
- 2008-05-01
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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TORIMARU Tadahiko
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
- 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
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- A Multicomponent Model of Radiation-induced Segregation for Commercial Stainless Steels
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- 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
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- 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