304不锈钢在核电站二回路水环境中的应力腐蚀开裂行为  

Stress Corrosion Cracking Behavior of 304L Stainless Steel in Secondary Loop of PWR Environment

作　　者：关矞心[1] 李成涛[1] 武焕春 方可伟[1] 罗坤杰[1] 王力[1] 薛飞[1] 

机构地区：[1]苏州热工研究院寿命评估中心,苏州215004

出　　处：《腐蚀与防护》2018年第3期198-201,共4页Corrosion & Protection

摘　　要：采用慢应变速率试验评价了在模拟压水堆核电站二回路中,氨、乙醇胺、氨+乙醇胺三种pH调节剂对304不锈钢抗应力腐蚀性能的影响,并通过扫描电镜对材料断口形貌进行观察。结果表明:304L不锈钢在三种模拟溶液中具有应力腐蚀敏感性,且应力腐蚀敏感性相当。The effect of ammonia, ethanolamine, mixture of ammonia and ethanolamine on stress corrosion cracking （SCC） of 304 stainless steel in simulated secondary loop of PWR environment was investigated using slow strain rate tests （SSRT）. And the fracture morphology of specimens was analyzed by scanning electron microscopy （SEM）. The results showed that 304 stainless steel had similar susceptibility to SCC in different simulated solutions.

关 键 词：304不锈钢 应力腐蚀开裂 核电 高温水 

分 类 号：TG172.82[金属学及工艺—金属表面处理]