反应堆压力容器接管嘴马鞍面缺陷的断裂力学分析

Fracture Analysis for Flaw on Reactor Pressure Vessel Outlet Nozzle

摘要: 某核电厂大修时发现反应堆压力容器均在出口接管嘴不锈钢堆焊层出现局部表面损伤痕迹，损伤最深处约为1.27 mm。本文采用ANSYS程序，依据相应规范，对反应堆压力容器出口接管嘴缺陷进行快速断裂力学分析和疲劳裂纹扩展分析。分析内容包含缺陷的包络和假设、应力计算、应力强度因子计算、疲劳裂纹扩展尺寸计算和Ⅱ、Ⅲ、Ⅳ工况及水压试验工况下的断裂力学分析评估。分析结果满足规范要求。

Abstract: Some local surface flaws were found by nuclear power plant at inspecting. These flaws were located on the stainless steel cladding of reactor pressure vessel outlet nozzle, which the maximal depth was 1.27 mm. According to the relative rules, the fast fracture and fatigue crack propagation analysis was performed with the ANSYS code in this paper. The analysis content includes a postulated reference crack, normal stress calculation, stress intensity factors calculation, the dimensions calculation of fatigue crack propagation, and fracture analyses under the conditionsⅡ, Ⅲ, Ⅳ and hydro-test conditions. The analysis results are shown to meet requirement of the RCC-M rule.