高橋 常夫 | Institute of Nuclear Safety System, Inc.
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概要
Institute of Nuclear Safety System, Inc. | 論文
- Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water : Effect of Chromium Content in Alloys and Dissolved Hydrogen
- Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (V) Characterization of Oxide Film with Multilateral Surface Analyses
- Microstructural Characterization of SCC Crack Tip and Oxide Film for SUS 316 Stainless Steel in Simulated PWR Primary Water at 320℃
- 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