摘要
为满足核反应堆压力容器40NCDV7-03主螺栓高屈服强度和抗拉强度,以及对塑性和冲击韧性的较高要求,设计多种热处理工艺方案,用试料进行模拟热处理。然后通过对试料的拉伸和冲击检测结果进行对比分析,确定合理的热处理工艺。实践证明热处理工艺行之有效。
Several heat treatment process schemes designed for 40NCDV7-03 stud that requires high yield strength,tensile strength,plasticity and toughness because of its application for the pressure vessel of nuclear reactors were simulated with test pieces for analysis.The tensile and impact test results of the test pieces are analyzed and compared to determine a proper process scheme.The practice has proved the process scheme is effective.
出处
《一重技术》
2021年第1期28-31,共4页
CFHI Technology
