摘要
核压力容器(reactor pressure vessel,RPV)材料的性能研究对保证核反应堆安全运行非常重要,鉴于辐照环境的限制,开展国产核压力容器材料A508-3钢的小冲杆试验研究很有必要。用小冲杆试验方法研究了A508-3钢的强度和韧性,建立了小冲杆试验结果与标准试验结果之间的关系,即屈服强度和屈服力之间的线性关系、抗拉强度和最大载荷之间的线性关系,验证了冲击试验得到的韧脆转变温度与小冲秆实验得到的韧脆转变温度之间的非线性关系,最后,对实验及数据处理中存在的问题进行了探讨。
The study on performance of the reactor pressure vessel is one of the key issues for the safe and reliable operation.Since the limitation of irradiation condition,small punch test was used to study the performance of the reactor pressure volume materials.The intensity and toughness of the domestic A508-3 steel was studied.The relations between the results of small punch test and the standard test was given.That is the relation of the yield strength and the yield stress,the relation of the ultimate strength and the ultimate stress,the relation of the ductile brittle transition temperature from impact test and from small punch test.Some issues about the experiment and the date dealing were discussed.
出处
《华北电力大学学报(自然科学版)》
CAS
北大核心
2011年第3期106-112,共7页
Journal of North China Electric Power University:Natural Science Edition
基金
973国家重点基础研究课题(2006CB605003)