摘 要：为有效应对各种事故工况，缓解事故后果，核电厂依据相应标准开发建立事故处理规程体系，确保核电厂的安全。文章以蒸汽发生器高水位响应规程为例介绍了第三代压水堆核电厂“华龙一号”事故处理规程的开发过程。在保证事故处理策略与导则一致的基础上扩展信息，为操纵员提供详细而准确的操作指令。通过验证和确认过程查找影响事故处理规程可用性的偏差项并提出修改方案。说明了“华龙一号”事故处理规程的合理性和有效性。
关键词：三代压水堆核电厂；华龙一号；事故处理规程；蒸汽发生器高水位
DOI:10.19850/j.cnki.2096-4706.2021.03.009
中图分类号：TL35 文献标识码：A 文章编号：2096-4706（2021）03-0032-05
Development of Steam Generator High Level Response Procedure
LIU Haiyu
（China Nuclear Power Engineering Co.，Ltd.，Beijing 100840，China）
Abstract：In order to effectively deal with various accident conditions and mitigate the consequences of accidents，nuclear power plants develop and establish accident handling procedures system according to corresponding standards to ensure the safety of nuclear power plants. Taking the high level response procedure of steam generator as an example，this paper introduces the development process of “HPR 1000” accident handling procedure of the third generation PWR nuclear power plant. On the basis of ensuring that the accident handling strategy is consistent with the guidelines，the information is expanded to provide detailed and accurate operation instructions for operators. Through the verification and validation process，the deviation items that affect the usability of accident handling procedures are found and the modification scheme is proposed. The rationality and effectiveness of “HPR 1000” accident handling procedures are explained.
Keywords：third generation PWR nuclear power plant；HPR 1000；accident handling procedure；steam generator high level
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作者简介：刘海宇（1982—），男，汉族，黑龙江人，高级工 程师，硕士，研究方向：核电厂运行安全策略开发。