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

作　　者：梅乐[1] 张俊宝[1] 王永东[1] 黄逸峰[1] 王秉熙 郑明光[1] MEI Le;ZHANG Junbao;WANG Yongdong;HUANG Yifeng;WANG Bingxi;ZHENG Mingguang(Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.,Shanghai 200233,China)

机构地区：[1]上海核工程研究设计院股份有限公司,上海200233

出　　处：《压力容器》2024年第2期1-6,共6页Pressure Vessel Technology

基　　金：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)。

摘　　要：通过模拟国内三代核电压水堆反应堆压力容器环焊缝,分别采用国产焊接材料和进口焊接材料,在焊接工艺性能、焊缝金属化学成分、拉伸、冲击韧性、落锤和低周疲劳试验等方面进行了对比分析。结果表明,国产和进口焊接材料的焊接工艺性能和焊缝金属力学性能均相当;焊接试件不同厚度取样位置的焊缝金属-28.3℃冲击吸收能量平均值都大于90 J,有较大的设计裕量。该国产焊接材料已应用于国内某三代核电机组反应堆压力容器,为进一步推广应用提供技术支撑。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 

分 类 号：TH49[机械工程—机械制造及自动化] TL351[核科学技术—核技术及应用] TG113.25[金属学及工艺—物理冶金]