摘要
ASME和RCC-M规范中规定了核级设备简化的弹塑性疲劳分析方法。规范中规定了泊松比效应和应力应变非线性导致的塑性修正因子(K_e)。RCC-M规范提出了分别适用于机械载荷和热载荷作用下的塑性修正因子。文中对蒸汽发生器主给水接管隔热套管进行疲劳分析,采用上述修正因子进行塑性修正并比较。结果表明在总应力中热应力占主导的情况下,ASME规定的塑性修正系数最为保守,RCC-M规定的塑性修正系数次之,泊松比效应导致的塑性修正因子保守性最小。
A simplified elastic-plastic fatigue analysis method for nuclear componets is presented in ASEM and RCC-M codes. The codes also provide plastic strain correction factors（Ke） due to poisson coefficient effect and nonlinear constitutive relations. RCC-M code defines two values for the stress due to mechanical loading and thermal loading respectively. The plastic strain correction factors are compared in the fatigue analysis of a thermal sleeve. The results show that plastic strain correction factor of ASME code is most conservative, RCC-M code takes next place and poisson coefficient effect is the least in this case of predominant thermal loading.
出处
《机械工程师》
2017年第1期67-70,共4页
Mechanical Engineer
关键词
核级设备
简化弹塑性疲劳分析
泊松比效应
塑性应变修正因子
nuclear componets
simplified elastic-plastic fatigue analysis
poisson coefficient effect
plastic strain correction factor
