某台国产压水堆压力容器锻件材料断裂韧性韧脆转变的参考温度

摘要

采用紧凑拉伸C（T）试样测试了某台国产反应堆压力容器用508-Ⅲ锻件的主曲线参考温度T0。为了方便今后在热室中进行辐照材料的断裂韧性试验，专门修改了C （T）试样的前端面设计。有限元分析和采用修改、未经修改的C （T）试样的试验结果均表明，对试样的修改不会影响断裂韧性试验。发现C（T）试样测得的T0值与前期采用三点弯曲SE（B）试样确定的T0值仅相差约1℃。为此详细探讨了ASTME1921标准第1．3和5．7条款有关试样形式对T0的影响，试验结果印证了这些条款的阐述，所测得的T0试验值接近材料的T0平均值。%This study experimentally evaluates the use of compact tension specimen(C(T)specimen)to determine the master curve reference temperature,T0 ,for the homemade 508-Ⅲ forging of a homemade reactor pressure vessel.The design for the front face of the C (T)specimen was modified such that the specimen can be conveniently operated in the hotcell for the future testing on the irradiated materials.The results of FEA and experiments using the modified and unmodified C(T)specimens show that the modi-fied design for the specimen would not affect fracture toughness testing.The difference in T0 values be-tween the C(T)specimens and the single-edge notched bend specimens(SE(B)specimen)is approxi-mately 1 ℃.The sections 1.3 and 5.7 of ASTME1921 are discussed.It is concluded that the experimen-tal results support the content of these sections and are close to the average T0 value of the material.