Fracture Analysis for Flaw on Reactor Pressure Vessel Outlet Nozzle

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.