压水堆核级承压容器缺陷返修技术

根据核安全分级,压水堆核电站核级承压容器在建造过程中,可采用ASME《锅炉与压力容器规范》B＆PVC第Ⅲ卷各分卷的要求进行建造;在投产运行过程中,可根据ASME B＆PVC第Ⅺ卷的要求进行在役检查。核级承压容器在建造过程中和在役检查过程中,会发现母材或焊缝缺陷,需根据相应的技术要求进行返修。根据ASME B＆PVC规范,对于不同阶段的缺陷返修技术,包括免做焊后热处理PWHT的回火焊道技术,进行了分析和归纳,为我国核级承压容器的缺陷返修工艺提供技术参考。

Defect Repair Technology of Nuclear Safety Related Pressure-retaining Vessel in Pressurized Water Reactor

Based on the nuclear safety related classification,the nuclear safety related pressure-retaining vessels in pressurized water reactor（ PWR） can be constructed per the subsection requirements in the Section Ⅲ,and be in-service inspected per the requirements in the Section Ⅺ of the ASME Boiler and Pressure Vessel Code B＆PVC. Both in the construction period and the subsequence in-service inspection period,some defects of base material or weld would be found and be repaired according to related technical requirements. Based on the ASME B＆PVC,the defect repair technology including the temper bead welding process without postweld heat treatment PWHT is analyzed and summarized with a view to provide a technical reference to the defect repair technology of pressure-retaining vessel in China.