压力容器2024，Vol.41Issue(2)：1-6,6.DOI:10.3969/j.issn.1001-4837.2024.02.001
三代核电反应堆压力容器低合金钢焊缝性能对比分析
Comparison and investigation on the properties of low-alloy steel weld metal in the reactor pressure vessel of the third generation nuclear power reactor
摘要
Abstract
By simulating the girth weld of the pressure vessel of the third generation pressurized water reactor in China,the domestic welding material and imported welding material were comparatively analyzed in terms of welding process performance,weld metal chemical composition,tensile strength,impact toughness,drop-weight and low-cycle fatigue tests.The results show that the welding process performance and mechanical properties of the weld metals of domestic and imported welding materials are equivalent.The average impact absorption energy at-28.3℃of the weld metal at different sampling positions of the test weldment is greater than 90 J,indicating a significant design margin.At present,the domestic welding materials have been applied in the pressure vessels of the third generation nuclear power plant in China,and are expected to be further applied in other plants in the future.关键词
反应堆压力容器/SA-508 Gr.3 Cl.1钢/国产焊材/焊缝性能Key words
reactor pressure vessel/SA-508 Gr.3 Cl.1 steel/domestic welding consumables/weld metal properties分类
机械制造引用本文复制引用
梅乐,张俊宝,王永东,黄逸峰,王秉熙,郑明光..三代核电反应堆压力容器低合金钢焊缝性能对比分析[J].压力容器,2024,41(2):1-6,6.基金项目
国家重点研发计划"在役核电站重要构筑物及设备材料老化退化行为规律与预测模型研究"(2019YFB1900901) （2019YFB1900901）
