核电厂技术规格书冷却剂放射性比活度运行限制条件确定方法研究

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英文篇名：Study on limit condition for operation in technical specifications of the radioactive specific activity in coolant of nuclear power plant 作者：付亚茹 ; 潘楠 ; 梅其良 ; 李怀斌 ; 毛兰方 英文作者：FU Yaru;PAN Nan;MEI Qiliang;LI Huaibin;MAO Lanfang;Shanghai Nuclear Engineering Research & Design Institute; 关键词：技术规格书 ; 碘 ; 比活度 ; 运行限制条件 ; AP1000 英文关键词：technical specifications;;iodine;;specific activity;;limit condition for operation;;AP1000 中文刊名：辐射防护 英文刊名：Radiation Protection 机构：上海核工程研究设计院有限公司; 出版日期：2019-01-20 出版单位：辐射防护 年：2019 期：01 语种：中文; 页：43-47 页数：5 CN：14-1143/TL ISSN：1000-8187 分类号：TM623

摘要

本文通过对西屋标准电厂技术规格书中一回路冷却剂放射性比活度限值的研究,揭示了限值制定的背景及含义,有助于对技术规格书中相关规定的深入理解和后续的执行。通过AP1000电厂与西屋标准技术规格书的比较可知,AP1000电厂技术规格书用剂量等效~(133)Xe比活度限值替代了西屋标准技术规格书中的总放射性比活度限值,剂量等效~(131)I比活度和~(133)Xe比活度限值均基于设计基准0.25%燃料包壳破损率计算得到,屏蔽设计、三废处理系统设计和事故后果分析等所采用的源项是一致的。最后,结合国内标准要求给出了可以对技术规格书中碘尖峰时比活度限值进行调整以及剂量等效~(131)I和~(133)Xe比活度限值可以根据0.25%燃料破损率计算数据进行调整的建议。
        The background and meaning of the limits formulation were revealed based on the study of the specific activity limits of primary coolant in Westinghouse standard specifications. This is helpful for the in-depth understanding and follow-up implementation of the relevant operation provisions. Through the comparison between AP1000 power plant specifications and Westinghouse standard specifications, it is found that the total specific radioactivity limit in AP1000 power plant specifications is replaced by the dose equivalent of ~(133)Xe specific activity limit in AP1000 power plant specifications. The dose equivalent of ~(131)I and ~(133)Xe specific activity limit are calculated based on the design basis of 0.25% fuel cladding defect. The source terms used in shielding design, waste treatment system design and accident radioactive consequence analysis are consistent. Finally, combined with the requirements of domestic regulations and standards, some suggestions were given on adjusting the iodine spike specific activity limits and dose equivalent of ~(131)I and ~(133)Xe specific activity limit according to the source terms of 0.25% fuel cladding defect.

引文

[1] U.S. Nuclear Regulatory Commission. Standard technical specifications Westinghouse plants:NUREG-1431[S]. Rev.4. Office of Nuclear Reactor Regulation. 2012-4.
    [2] U.S. Nuclear Regulatory Commission. 10 CFR 100 Reactor site criteria[R]. Office of Nuclear Reactor Regulation. 2016.
    [3] Westinghouse. AP1000 design control document[R]. 2012.
    [4] U.S. Nuclear Regulatory Commission. Standard review plan for the review of safety analysis reports for nuclear power plants:NUREG-0800[S]. Office of Nuclear Reactor Regulation. 2007.
    [5] 苏州热工研究院有限公司,环境保护部核与辐射安全中心. 核动力厂环境辐射防护规定:GB 6249—2011[S]. 北京:中国标准出版社.2011.Suzhou Nuclear Power Research Institute, Co.Ltd., Nuclear and Radiation Safety Center,MEPA. Regulations for environmental radiation protection of nuclear power plant: GB 6249—2011[S].Beijing: China Standards Press,2011.