【摘要】 核一级部件的断裂韧度要求反映在 ASME和 RCC- M规范中 ,即 KIR- (T - RTNDT)基准曲线。KIR包括 KIa、KId和 KJIc。KJIc的测试国内外已有标准方法 ,而 KIa的测试只有美国公布了正式标准 ,KId的测试国内外均没有标准方法可循。因此 ,为研究核电材料断裂韧度 ,首先建立了相应的测试方法 ,在此基础上试验了国产核一级容器钢 5 0 8- 3的动、静态断裂韧度 KIa、KId、KIc,获得了不同温度下的数据 ,并与 ASME和 RCC- M规范中的基准曲线作了比较。结果表明 ,国产 5 0 8- 3钢的动、静态断裂韧度能满足核一级部件的要求更多还原

【Abstract】 The requirements for first class nuclear reactor components in ASME and RCC M Standards were represented by K IR -( T-RT NDT ) curve. It contains K Ia , K Id and K J Ic . For K J Ic , there are the Chinese and foreign standard test methods. For K Ia , there is only one standard test method issued by U.S.A. But there is no test method at all for K Id . So in order to study or test fracture toughness of the nuclear reactor materials, first the standard test method was studied and established and then the static and dynamic fracture toughness of nuclear reactor vessel steel 508 3, and K Ia , K Id , K J Ic at different temperatures were obtained. The results showed that the static and dynamic fracture toughness of steel 508 3 satisfies the requirements for first class nuclear reactor components.更多还原