Development of Micro Tensile Testing Method in an FIB System for Evaluating Grain Boundary Strength
スポンサーリンク
概要
- 論文の詳細を見る
- 2011-01-01
著者
-
Fukuya Koji
Institute Of Nuclear Safety System
-
FUJII Katsuhiko
Institute of Nuclear Safety System
-
Fujii Katsuhiko
Institute Of Nuclear Safety System Inc.
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
- 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