摘要
ASME标准是最为广泛、内容最为详尽的压力容器标准,在核岛主设备制造及核电站安装建设的设计、制造、检验、质量保证、运行维护等过程中广泛使用。国内核电站堆型主流的三代核电技术CAP 1000及CAP 1400、小堆等堆型、四代核电技术高温气冷堆、快中子实验堆、低温堆等堆型,所用的标准体系均为美国的ASME核电标准体系。本文从ASME标准第Ⅸ卷焊接工艺评定篇中评定的制定、母材及焊材分组、焊后热处理及焊缝厚度覆盖范围等方面对应用ASME标准进行工艺评定过程中需要注意的问题进行分析。分析表明,根据焊接冶金性能、机械性能等影响焊缝性能的要素,焊接工艺评定的各要素都具有相应的评定覆盖性,评定制定的过程中必须严格遵循各评定要素的覆盖范围。
More and more the third generation nuclear power plant manufacturing are substituted for the second half generation nuclear power plant manufacturing in China gradually,and the standard of nuclear power plant manufacturing according to ASME code will be used more and more than RCC-M code.This paper analyses the welding variables for welding procedure qualification basing on listing welding procedure qualification of one equipment manufacturing,base metal and welding material assignments,postweld heat treatment and range of thickness of base metal qualified.It concludes that assignments are based essentially on comparable base metal characteristics,such as composition on weldability,welding material and mechanical properties and so on,each welding variables has its range of qualification,and range of qualification welding variables shall be performed totally according to ASME.
作者
张丹萍
霍肖寒
黎振龙
ZHANG Danping;HUO Xiaohan;LI Zhenlong(Dongfang(Guangzhou)Heavy Machinery Co.,Ltd.,511455,Guangzhou,China;China-Ukraine Institute of Welding,Guangdong Academy of Sciences,511455,Guangzhou,China)
出处
《东方电气评论》
2024年第6期44-46,54,共4页
Dongfang Electric Review