摘要
依据法规要求和国外的研究成果 ,对压水堆核电厂反应堆压力容器承压热冲击 (PTS)的研究方法进行阐述。研究工作考虑和比较了不同的裂纹尺寸、不同的裂纹类型和不同的PTS瞬态的情况 ,进而确定该RPV在哪种裂纹和哪种瞬态下最危险。热弹性和热弹塑性两种材料模式运用于RPV的应力计算 ,分析中考虑了不锈钢堆焊层对断裂分析的影响。
Based on the requirements of western codes and rules and the research achievements, the analysis procedures for structure integrity of reactor pressure vessel (RPV) under pressurized thermal shock (PTS) were presented in this paper. The models with the flaw depth range a/w=0.05～0.9 were used to probe what kind of flaw and what kind of transient are most detrimental for the RPV in the end of life (EOL). Both the linear elastic and elastic-plastic material models were used in the stress analysis and fracture mechanics analysis. The influence of the stainless steel cladding on the fracture analysis were investigated.
出处
《压力容器》
2004年第10期5-9,13,共6页
Pressure Vessel Technology
关键词
反应堆压力容器
承压热冲击
结构完整性
表面裂纹和深埋裂纹
reactor pressure vessel
pressurized thermal shock
structure integrity
surface flaw and sub-surface flaw
