Separation of Microstructural and Microchemical Effects in Irradiation Assisted Stress Corrosion Cracking using Post-irradiation Annealing
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概要
- 論文の詳細を見る
Post-irradiation annealing (PIA) was conducted in order to clarify the role of microstructural and microchemical effects on irradiation assisted stress corrosion cracking (IASCC) susceptibility in simulated pressurized water reactor (PWR) primary water. Microstructures, hardening, radiation-induced segregation and IASCC susceptibility were examined in cold-worked SUS 316 stainless steels irradiated to 25 dpa in a PWR after annealing at 673–823 K for 1 h. IASCC susceptibility, microstructures and hardening recovered as the annealing temperature increased whereas the grain boundary segregation of Cr and Ni remained almost unchanged. The results suggested that the change in IASCC susceptibility due to annealing is not attributed to the change in grain boundary segregation but to the change in microstructures and hardening. The fact that a smaller recovery of radiation hardening caused a larger IASCC susceptibility suggested that a threshold hardening level exists for the occurrence of IASCC.
- 社団法人 日本原子力学会の論文
- 2004-12-25
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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FUJII Katsuhiko
Institute of Nuclear Safety System
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TORIMARU Tadahiko
Nippon Nuclear Fuel Development
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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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Fukuya K
Institute Of Nuclear Safety System
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Fukuya Kohji
Institute Of Nuclear Safety System
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Nakano Morihito
Institute Of Nuclear Safety System Inc.
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Fujii K
Institute Of Nuclear Safety System
関連論文
- Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water : Effect of Chromium Content in Alloys and Dissolved Hydrogen
- 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
- 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