压力容器Issue(3)：62-69,8.DOI:10.3969/j.issn.1001-4837.2014.03.010
压水堆核级承压容器缺陷返修技术
Defect Repair Technology of Nuclear Safety Related Pressure-retaining Vessel in Pressurized Water Reactor
郑东宏 1王志强 1王勇 1王江涛 1褚争1
作者信息
- 1. 国核工程有限公司，山东海阳 265116
- 折叠
摘要
Abstract
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 .关键词
压水反应堆/承压容器/缺陷返修/回火焊道焊接Key words
pressurized water reactor/pressure-retaining vessel/defect repair/temper bead welding分类
机械制造引用本文复制引用
郑东宏,王志强,王勇,王江涛,褚争..压水堆核级承压容器缺陷返修技术[J].压力容器,2014,(3):62-69,8.
