核电站用不锈钢在高温高压水中应力腐蚀开裂行为的研究进展
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Research Progress on Stress Corrosion Cracking of Stainless Steel for Nuclear Power Plant in High-temperature and High-pressure Water
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图4. pH对304L、316L、法国Z6CND17.12奥氏体不锈钢SCC的影响[ |
Fig.4. Effects of pH on SCC of 304L, 316L and France Z6CND17.12 austenitic stainless steel[ |
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