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  

The Fracture Toughness Reference Temperature for the Forging of a Homemade Reactor Pressure Vessel

作　　者：曹昱澎[1,2] 惠虎[1] 轩福贞[1] 李辉[2] 贺寅彪[2] 王佳欢[1] 王秉熙 

机构地区：[1]华东理工大学承压系统安全科学教育部重点实验室,上海200237 [2]上海核工程研究设计院工程设备所,上海200233

出　　处：《压力容器》2013年第11期8-13,28,共7页Pressure Vessel Technology

基　　金：国家高技术研究发展计划(863计划)项目(2012AA040105);上海市博士后科研资助计划项目(12R21420600)

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ASTM E1921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, To, 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 To 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 ASTM E1921 are discussed. It is concluded that the experimen tal results support the content of these sections and are close to the average TO value of the material.

关 键 词：紧凑拉伸试样 508-Ⅲ锻件 主曲线 ASTM E1921 韧脆转变断裂韧性 

分 类 号：TH49[机械工程—机械制造及自动化]