摘要
简要介绍了采用慢应变速率试验(SSRT)、U型弯曲和C形环试验等技术,分别对800合金、304和316及316Ti不锈钢、A533B压力容器用钢在模拟核反应堆环境中的应力腐蚀破裂(SCC)敏感性进行的试验研究的一些主要结果;并结合电化学测试和表面膜俄歇电子能谱(AES)分析结果进行了讨论;提出了高温水中SCC加速试验方法选择原则以及SSRT的敏感评价参数的建议。
The susceptibility to stress corrosion cracking (SCO of alloy 800, stainless steels 304, 316 and 316Ti, pressure vessel steel A533B in simulated reactor environments was investigated using slow strain rate tests (SSRT), U-bend and C-ring tests, respectively, complemented by electrochemical measurements and Auger electron spectroscopy (AES) analyses. Some most important results are briefly introduced. Suggestions on choosing the acce lerating testing methods and the most sensitive evaluation parameter for SSRT are proposed.
出处
《理化检验（物理分册）》
CAS
1996年第5期7-12,共6页
Physical Testing and Chemical Analysis(Part A:Physical Testing)
关键词
核电材料
模拟反应堆环境
应力腐蚀破裂
Nuclear power materials, Simulated reactor environment, Stress corrosion cracking (SCC), Testing and evaluation
