压力容器2025，Vol.42Issue(5)：1-11,11.DOI:10.3969/j.issn.1001-4837.2025.05.001
核电稳压器筒体内壁不锈钢堆焊层309L过渡层裂纹产生机理分析
Analysis of crack formation mechanism in 309L transition layer of stainless steel cladding on inner wall of nuclear power pressurizer vessel
摘要
Abstract
To address the problem of microcrack defects in the 309L transition layer of the stainless steel cladding on the inner wall of a nuclear power pressurizer vessel,methods including scanning electron microscopy(SEM),X-ray diffraction(XRD),optical microscopy(OM),and energy dispersive spectroscopy(EDS)were used to conduct in-depth research on intercepted samples with cracks.The results show that these microcracks are high-temperature ductility-dip cracks,characterized by intergranular propagation accompanied by grain boundary sliding,with a large amount of oxides present at the grain boundaries.Through reproduction tests and combined with actual working conditions,it was found that the main cause of crack formation is insufficient protection of the welding zone during the welding process,leading to the precipitation of grain boundary oxides,which subsequently initiate and propagate under welding stress.The developed reproduction test method for high-temperature ductility-dip cracks effectively verified the nature and cause of the cracks,providing an important theoretical basis for the improvement and optimization of cladding processes in nuclear power equipment,which is of great significance for ensuring the safe operation of nuclear power equipment.关键词
核电稳压器/不锈钢堆焊层/裂纹Key words
nuclear power pressurizer/stainless steel cladding layer/cracks分类
机械制造引用本文复制引用
王炜铭,张茂龙,张明明,余春,杨淼森,罗庆,孙志远,胡光敏,陆皓,纵海..核电稳压器筒体内壁不锈钢堆焊层309L过渡层裂纹产生机理分析[J].压力容器,2025,42(5):1-11,11.基金项目
国家自然科学基金项目(52275354) （52275354）
