Integration and Future Development of Technical Standards for PWR Nuclear Pressure Equipment

Feifei Wu, Zhenbang Dong, Jun Huang, Shangyuan Liu
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Abstract

The development of nuclear power safety and the global procurement of nuclear power equipment have put forward an urgent need for the integration of nuclear power standards. In this paper, the development history and technical status of the localization of pressure equipment in China’s PWR nuclear power plants is introduced. This paper expounds the technology innovation and engineering experience of China’s independently-developed third-generation PWR nuclear power based on “HPR 1000” and “CAP 1400”, and the main goals, principles and basic ideas of the integration of technical standards for nuclear pressure equipment by sorting out and analyzing the list of topics in the fields of materials, design, manufacturing, welding, non-destructive testing and other professional fields involved in the integration of China’s nuclear pressure equipment standards, comparing with the technical topics involved in the current work of the SDO Integration Committee, and further discussing the differences and connections. This paper discusses the future development trend of nuclear pressure equipment in pressurized water reactor nuclear power plants and the demand for standardization of key technologies, and proposes the main problems that should be paid attention to and solved in the next step in the integration of nuclear pressure equipment standards.
压水堆核压力设备技术标准的整合与未来发展
核电安全的发展和核电设备的全球采购对核电标准的整合提出了迫切的需求。介绍了中国压水堆核电站压力设备国产化的发展历史和技术现状。本文通过对材料、设计、制造、焊接、核电等领域课题清单的整理分析,阐述了中国自主开发的第三代压水堆核电在“HPR 1000”和“CAP 1400”基础上的技术创新和工程经验,以及核压设备技术标准整合的主要目标、原则和基本思路。将无损检测等专业领域所涉及的中国核压设备标准整合,与SDO整合委员会目前工作所涉及的技术课题进行比较,并进一步探讨其差异和联系。论述了压水堆核电站核压设备的未来发展趋势和关键技术的标准化需求,提出了下一步核压设备标准整合应注意和解决的主要问题。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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