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
焦洋, 张胜寒(), 檀玉
Research Progress on Stress Corrosion Cracking of Stainless Steel for Nuclear Power Plant in High-temperature and High-pressure Water
JIAO Yang, ZHANG Shenghan(), TAN Yu

图4. pH对304L、316L、法国Z6CND17.12奥氏体不锈钢SCC的影响[47-49]

Fig.4. Effects of pH on SCC of 304L, 316L and France Z6CND17.12 austenitic stainless steel[47-49]