摘要
核反应堆堆内构件、零部件及焊缝、焊点较多,存在焊接接头型式、母材及其厚度、焊接工艺方法、焊接位置和方向等的不同,导致焊接工艺评定的复杂性。文章介绍了焊接工艺评定的一般变素、堆内构件焊缝分布及堆内构件的焊接工艺评定。并针对RCC-M规范、ASME规范及国内相关标准对焊接工艺评定要求的差异,结合堆内构件焊接工艺评定过程中尺寸稳定化处理、焊接接头的横向拉伸试样、手工焊与自动焊的定义、破坏性试验的复验要求等方面的争议,提出了个人的理解和认识。
The requirements for qualification of welding procedure are stricter,especially in manufacture of nuclear island equipment.More than ten thousand welds exist,and different types of joint,welding process,base metal and its thickness,welding position and direction,all this leads to the complexity of qualification of welding procedure in reactor internals.The paper introduces the variables,welds distribution and qualification of welding procedure.At last,for different requirements of RCC-M code,ASME code and domestic standards,the paper puts forward its own opinions and understanding to the disputes of dimensional stability treatment,transverse weld tensile test,definition of manual welding and automatic welding and requirements of retest.
出处
《中国核电》
2012年第4期318-324,共7页
China Nuclear Power
关键词
核反应堆
堆内构件
焊接工艺评定
理解与争议
nuclear reactor
reactor internals
qualification of welding procedure
comprehension and dispute
