反应堆压力容器用钢的淬透性问题  

Hardenability of nuclear reactor pressure vessel steels

作　　者：李昌义[1] 刘正东[1] 林肇杰[1] 金明[1] 

机构地区：[1]钢铁研究总院结构材料研究所,北京100081

出　　处：《材料热处理学报》2011年第6期68-72,共5页Transactions of Materials and Heat Treatment

基　　金：国家重大专项计划(2010ZX06004-016)

摘　　要：利用Formastor-FⅡ全自动相变测量装置测试了SA508-3钢和SA508-4N钢的相变点,得出了两种核压力容器用钢的完整CCT曲线,并在试验基础上对SA508-3和SA508-4N钢的淬透性极限问题进行了探讨。结果表明:SA508-4N钢的强度、低温韧性、淬透性极限相比于SA508-3钢有显著提高。随着反应堆压力容器向大型化和一体化方向发展,具有更高强韧性和淬透性的SA508-4N钢将可能逐步替代SA508-3钢而获得工程应用。The phase transformation temperatures and complete CCT curves of SA508-3 and SA508-4N steels were measured by a Formastor-FⅡ phase transformation instrument.The limitation of hardenability of SA508-3 and SA508-4N steels was experimentally investigated.The results show that the strength,low temperature toughness and the hardenability limitation of SA508-4N steel exhibited significant improvement compared with SA508-3 steel.As size of reactor pressure vessel increases,SA508-4N steel with higher strength,toughness and hardenability will substitute for SA508-3 steel in engineering application gradually.

关 键 词：核压力容器 SA508-3钢 SA508-4N钢 淬透性极限 

分 类 号：TG142.41[一般工业技术—材料科学与工程]