CAJ | 학술논문

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。
근거핵안전분급，압수퇴핵전참핵급승압용기재건조과정중，가채용ASME《과로여압력용기규범》B＆PVC제Ⅲ권각분권적요구진행건조；재투산운행과정중，가근거ASME B＆PVC제Ⅺ권적요구진행재역검사。핵급승압용기재건조과정중화재역검사과정중，회발현모재혹한봉결함，수근거상응적기술요구진행반수。근거ASME B＆PVC 규범，대우불동계단적결함반수기술，포괄면주한후열처리PWHT적회화한도기술，진행료분석화귀납，위아국핵급승압용기적결함반수공예제공기술삼고。
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 Ⅺof 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 techni-cal 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 .