国产A508-3钢辐照性能  

Mechanical Property of China A508-3 Steel after Neutron Irradiation

作　　者：林赟[1] 宁广胜[1] 张长义[1] 佟振峰[1] 杨文[1] 

机构地区：[1]中国原子能科学研究院反应堆工程研究设计所,北京102413

出　　处：《原子能科学技术》2016年第2期204-207,共4页Atomic Energy Science and Technology

基　　金：国家科技重大专项资助项目(2011ZX06004-002);国家重点基础研究发展计划资助项目(2011CB610503)

摘　　要：反应堆压力容器(RPV)作为反应堆寿期内不可更换的核心设备,是防止堆芯放射性泄漏的最主要屏障。本文针对国产压力容器材料A508-3钢,开展了一定剂量水平(约10×1019 cm-2,E≥1 MeV)的研究堆加速辐照试验,并进行了辐照后力学性能测试分析,包括拉伸性能和冲击性能测试。结果显示,辐照后在-100、20、288℃下,A508-3钢的屈服强度分别增加了83、108、52 MPa,抗拉强度分别增加了58、61、49 MPa,韧脆转变温度T41J增加了68℃,上平台能量降低了61J。A508-3钢辐照前后性能测试结果表明,在中子辐照至60a寿期后,A508-3钢仍能满足反应堆使用要求。Reactor pressure vessel （RPV） is the critical un-changeable component of the reactor during its service lifetime, which prevents the radioactive leak of the nuclear power plant core. The irradiation test （about 10×1019 cm-2, E≥1MeV） of the pres- sure vessel material of China A508-3 steel in research reactor was carried out, and the mechanics performance tests were carried out after the neutron irradiation, including tensile property and impact property. The results show that the yield strength increases by 83, 108 and 52 MPa, and the tensile strength increases by 58, 61 and 49 MPa at --100, Z0 and 288℃, respectively. The ductile-brittle transition temperature Z41J increases by 68℃, and the upper shelf energy decreases by 61 J. Meanwhile, by compa- ring the property of un-irradiated and irradiated material, after irradiated to the level of 60 a service life, A508-3 steel still meets the reactor operation requirement.

关 键 词：A508-3钢 中子辐照 辐照脆化 

分 类 号：TL341[核科学技术—核技术及应用]