某核电厂主泵—主管道焊缝冲击韧性偏低不符合项的审评  

The Review of the Non-conformance Item on the Impact Toughness Value Lower than the Allowable Value at the Main Coolant Pipeline-Reactor Coolant Pump Welded Joint

作　　者：方庆贤[1] 吴清可 朱宏[1] 刘振领 孙造占[1] 黄炳臣[1] 段红卫[1] 

机构地区：[1]国家环境保护总局核与辐射安全中心,北京100082 [2]机械科学研究院核设备安全与可靠性中心,北京100044

出　　处：《核安全》2007年第1期8-12,共5页Nuclear Safety

摘　　要：针对某核电厂主泵-主管道焊缝材料冲击韧性偏低这一不符合项,根据目前我国的核安全法规和俄罗斯有关的标准规范并结合国际上通用的核标准,针对这一不符合项提出了自己的审评见解和解决方案。并对该核电厂今后的运行提出了安全要求。For the non-conformance item on the value at the main coolant pipeline-reactor coolant pump tion scheme, based on the Chinese nuclear safety laws, al international nuclear standards. At the same time, we impact toughness value lower than the allowable welded joint we gave the review opinion and solu- Russian nuclear safety standards as well as gener- put forward the safety requirement for the nuclear power plant operation in future.

关 键 词：不符合项 审评 主泵-主管道焊缝 防脆断分析 LBB 

分 类 号：TM623[电气工程—电力系统及自动化]