Microstructural Characterization of SCC Crack Tip and Oxide Film for SUS 316 Stainless Steel in Simulated PWR Primary Water at 320℃
スポンサーリンク
概要
- 論文の詳細を見る
Recent studies on stress corrosion cracking (SCC) behaviors of austenitic stainless steels in hydrogenated high-temperature water show that low potential SCC (LPSCC) can occur on cold-worked SUS 316 stainless steel (hereinafter, 316SS). In this study, oxide films and crack tips on cold-worked 316SS exposed to hydrogenated high-temperature water were characterized using analytical transmission electron microscopy (ATEM), grazing incidence X-ray diffraction (GIXRD) and Auger electron spectroscopy (AES) in order to study the corrosion and SCC behaviors of these films and crack tips. A double layer structure was identified for the oxide film after a constant extension rate tensile (CERT) test. The outer layer was composed of large particles (0.2–3 μm) of Fe3O4 and the inner layer consisted mainly of fine particles (∼10 nm) of FeCr2O4. In addition, nickel enrichment was identified at the metal/oxide interface. Particles of Fe3O4 were also identified on the crack walls. These results indicate that the same electrochemical reactions had occurred inside and outside the crack. The crack tip area was filled with corrosion products of a chromium-rich oxide. In addition, nickel enrichment was observed at the crack tip. The formation of the nickel-enriched phase indicates that a selective dissolution reaction of iron and chromium occurred at the front of the LPSCC crack.
- 一般社団法人 日本原子力学会の論文
- 2005-02-25
著者
-
ARIOKA Koji
Institute of Nuclear Safety System, Inc.
-
FUJII Katsuhiko
Institute of Nuclear Safety System
-
Arioka Koji
Institute Of Nuclear Safety System Inc.
-
Terachi Takumi
Institute Of Nuclear Safety System Inc.
-
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
- 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
- Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (V) Characterization of Oxide Film with Multilateral Surface Analyses
- A Multicomponent Model of Radiation-induced Segregation for Commercial Stainless Steels
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Low Temperature Grain Boundary Diffusion of Chromium in SUS316 and 316L Stainless 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℃
- Evaluation of Internal Stress in Individual Grains of Cold-Rolled Stainless Steel by Energy Dispersive X-ray Diffraction
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels