Thermal-Mechanical Stress Analysis of PWR Pressure Vessel and Nozzles under Grid Load-Following Mode: Interim Report on the Effect of Cyclic Hardening Material Properties and Pre-existing Cracks on Stress Analysis Results

Mohanty, Subhasish¹  Soppet, William¹  Majumdar, Saurin¹  Natesan, Ken¹ 

[1] Argonne National Lab. (ANL), Argonne, IL (United States)

关键词: Environmental Fatigue;    Finite Element Method;    Grid Load Following;    Heat Transfer Analysis;    PWR;    Pressurized water reactor;    Thermal-Mechanical Stress Analysis;    XFEM;   

DOI  :  10.2172/1249554
RP-ID  :  ANL/LWRS--16/01
PID  :  OSTI ID: 1249554
Others  :  Other: 126541

学科分类：工程和技术（综合）

美国|英语

来源: SciTech Connect

【 摘 要 】

This report provides an update on an assessment of environmentally assisted fatigue for light water reactor components under extended service conditions. This report is a deliverable under the work package for environmentally assisted fatigue as part of DOE???s Light Water Reactor Sustainability Program. In a previous report (September 2015), we presented tensile and fatigue test data and related hardening material properties for 508 low-alloys steel base metal and other reactor metals. In this report, we present thermal-mechanical stress analysis of the reactor pressure vessel and its hot-leg and cold-leg nozzles based on estimated material properties. We also present results from thermal and thermal-mechanical stress analysis under reactor heat-up, cool-down, and grid load-following conditions. Analysis results are given with and without the presence of preexisting cracks in the reactor nozzles (axial or circumferential crack). In addition, results from validation stress analysis based on tensile and fatigue experiments are reported.