Methodology and Warm Prestressing Effect for Pressurized Thermal Shock Analysis in Nuclear Power Plant
(0) One potential challenge to the integrity of the reactor pressure vessel (RPV) in a pressurized water reactor is posed by pressurized thermal shock (PTS).Therefore, the safety of the RPV with regard to neutron embrittlement has to be analyzed.In this paper, the procedure and method for the structural integrity analysis of RPV subjected to PTS is presented.The FAVOR code is applied to calculate the probabilities for crack initiation and failure by considering crack distributions based on cracks observed in the Shoreham and PVRUF RPVs in the U.S.A local approach to fracture, i.e.the σ*-A* model is used to predict the warm prestressing (WPS) effect on the RPV integrity.The results show that the remaining stress contributes to the WPS effect, whereas the increase of fracture toughness is not completely attributed to the remaining stress.The modeled load paths predict a material toughness increase of 30-100%.
reactor pressure vessel pressurized thermal shock probabilistic fracture mechanics fracture toughness warm prestressing
Guian Qian Markus Niffenegger
Paul Scherrer Institute,Nuclear Energy and Safety Department,Laboratory for Nuclear Materials,5232 Villigen PSI,Switzerland
国际会议
2014 International Symposium on Structural Integrity,ISSI2014(2014国际结构完整性学术会议)
兰州
英文
49-58
2014-08-20（万方平台首次上网日期，不代表论文的发表时间）