核电站一回路关键设备材料热老化敏感性分析  

Investigation on Sensitive to Thermal Aging for Key Materials Used in Primary Circuit of Nuclear Power Plants

作　　者：余伟炜[1] 蒙新明[1] 姜家旺[1] 薛飞[2] 束国刚 刘伟[2] 

机构地区：[1]苏州热工研究院有限公司,江苏苏州215004 [2]清华大学材料科学与工程系,北京100084 [3]中广核工程有限公司,广东深圳518124

出　　处：《核电工程与技术》2014年第3期22-30,共9页Nuclear Power Engineering and Technology

摘　　要：本文对PWR核电站一回路关键设备用低合金钢、不锈钢、镍基合金和锆合金等材料进行了热老化敏感性分析。调研发现奥氏体不锈钢焊缝、铸造奥氏体不锈钢属于热老化脆化敏感材料，而高强螺栓用低合金钢、PH系列沉淀硬化不锈钢属于潜在热老化敏感性材料；相比之下，锻造奥氏体不锈钢、X－750、718、A－286、锆合金、600和690合金及其82／182、52／152型焊缝在PWR核电站运行环境下对热老化不敏感。通过对上述材料的热老化脆化机理和影响分析，提出了相应的建议和措施，为电站的老化管理提供参考。This paper reviewed the thermal aging embrittlement potential of materials used in Pressurized Water Reactors （PWRs）. The materials including low alloy steel, austenitic stainless steels, nickelbased alloys, and zirconium alloy were examined. It concludes that austenitie stainless steel welds and castings are susceptible to thermal aging embrittlement, the high strength low alloy bolting materials and PH stainless steels are potentially susceptible to thermal aging embrittlement at PWR operation environment. For the other materials, such as wrought austenitic stainless steels, Alloys X-750, 718, A-286, Zirconium alloy, Alloys 600 and 690, their weld metals Alloys 82/182 and 52/152, are not susceptible to thermal aging embrittlement under PWR environment. Based on the embrittlement mechanism analysis and effect investigation, suggestions are recommended in this paper to provide guidance for the aging management of NPPs.

关 键 词：热老化 脆化 核电站 老化管理 

分 类 号：TG142.25[一般工业技术—材料科学与工程]