文献类型：期刊文献

英文题名：Probabilistic structural integrity assessment for Inconel690 alloy steam generator tube with volume defect

作者：Huang, Song[1];Hui, Hu[1];Peng, Zhizhen[2]

机构：[1]East China Univ Sci & Technol, Sch Mech & Power Engn, Shanghai 200237, Peoples R China;[2]Suzhou Nucl Power Res Inst, Suzhou 215000, Peoples R China

年份：2021

卷号：371

外文期刊名：NUCLEAR ENGINEERING AND DESIGN

收录：;EI(收录号：20204909568107);WOS:【SCI-EXPANDED(收录号:WOS:000604780600002)】；

基金：This work was supported by CGNPC Peak Project (No. 2018-02-36000000-011).

语种：英文

外文关键词：Steam generator tube rupture; Probabilistic integrity assessment; Bursting pressure; Repair criterion; Fretting; Inconel690 alloy

摘要：Fit for service(FFS) assessment of Steam Generator Tube(SGT) plays a key role in safety operating of Pressurized Water Reactors. Engineering practices have emerged probabilistic method is a powerful tool in reducing redundant safety margin of FFS assessment strategy. The aim of this work is to develop a probabilistic structural integrity assessment method for typical Inconel690 alloy SGT with volume defect. The study consists of four parts: Firstly, an experiment program including tensile test, eddy current examination and SGT bursting test were introduced. Then, potential bursting pressure models were analyzed based on test dataset. Proper bursting pressure model was suggested. Thirdly, probabilistic bursting pressure prediction model was developed based on Monte Carlo Simulation. At last, parametric study was performed and an application instance on anti-vibration bar fretting wear was presented. The results indicated the proposed SGT structural integrity assessment method is less conservative than current repair criterions. This study represents a further step towards developing of smart FFS assessment of Nuclear Power Plant.