压水堆核电站在役机组更换控制棒驱动机构自动焊工艺研究

左智成; 李杰; 孙士杰; 陈英杰; 张建平

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压水堆核电站在役机组更换控制棒驱动机构自动焊工艺研究
Research on automatic welding technology of CRDM in in-service unit of PWR nuclear power plant
2019年49卷第12期页码：81-85
纸质出版：2019
DOI：
稿件说明：

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左智成, 李杰, 孙士杰, 等. 压水堆核电站在役机组更换控制棒驱动机构自动焊工艺研究[J]. 电焊机, 2019,49(12):81-85. DOI：

ZUO Zhicheng, LI Jie, SUN Shijie, et al. Research on automatic welding technology of CRDM in in-service unit of PWR nuclear power plant[J]. Eletric Welding Machine2019, 49(12): 81-85. DOI：

摘要

目前国内压水堆核电站在役机组控制棒驱动机构(CRDM)的更换维修主要被法国AREVA公司垄断

国内尚无一家公司具备CRDM在役更换的能力

开发一套完整的控制棒驱动机构在役更换工艺具有十分重要的意义。主要介绍压水堆核电站机组控制棒驱动机构在役更换涉及的下部密封焊缝自动焊操作要领及技术参数

结合试验过程

给出合适的操作参数

为后续控制棒驱动机构的在役更换提供借鉴与指导。

Abstract

At present

the replacement and maintenance of CRDM in in-service unit of PWR nuclear power plant in China

is mainly monopolized by AREVA

and no company has the capability to replace CRDM in in-service unit of PWR nuclear power plant.Therefore

the development of a complete progress of in-service unit replacement for CRDM is of great significance. This paper mainly introduces the automatic welding operation essentials and technical parameters of the lower sealing welds involved in the replacement of the CRDM in the PWR reactor unit in service. According to the process of stand-by test

the proper operation parameters are given

which can provide the reference for the following replacement of the CRDM in the PWR reactor unit in service.