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华龙一号后续机型安全系统配置与验证方案

Configuration and Validation Plan of the Safety System for AHPR1000 Reactor

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【作者】 崔怀明黄代顺陈伟马海福喻娜卢毅力张渝

【Author】 Cui Huaiming;Huang Daishun;Chen Wei;Ma Haifu;Yu Na;Lu Yili;Zhang Yu;National Key Laboratory of Nuclear Reactor Technology, Nuclear Power Institute of China;

【机构】 中国核动力研究设计院核反应堆技术全国重点实验室

【摘要】 随着自主三代压水堆核电机型华龙一号(HPR1000)在国内外批量化建造,为了进一步提升HPR1000的安全性、经济性、先进性、运行可靠性、环境友好性和智能化水平,中国核工业集团有限公司于2019年开始启动HPR1000后续机型(AHPR1000)的研发,其中安全系统/设施的设计创新是研发核心内容。AHPR1000机型安全系统/设施主要用于在事故工况下保证反应堆的安全和控制/缓解放射性物质的释放。本文针对AHPR1000机型安全系统配置,提出“非能动+能动”的设计理念,从顶层安全理念及设计原则出发,重点对安全功能、安全配置、事故应对策略、试验验证等方面进行了介绍。

【Abstract】 With the batch construction of the independently developed third-generation pressurized water reactor nuclear power plant HPR1000 at home and abroad, China National Nuclear Corporation(CNNC) initiated the development of its follow-up reactor(AHPR1000) in 2019 to further enhance the safety, economy, advancement, operational reliability, environmental friendliness, and intelligence level of HPR1000. The design innovation of safety systems and facilities is a core part of this development. The safety systems and facilities of the AHPR1000 reactor are mainly used to ensure reactor safety and control/contain radioactive material releases under accident conditions. This paper proposes a design concept combining "passive and active" systems for the safety system configuration of AHPR1000. Starting from the top-level safety philosophy and design principles, it focuses on introducing the safety functions, safety configuration, accident response strategies, and experimental validation.

  • 【文献出处】 核动力工程 ,Nuclear Power Engineering , 编辑部邮箱 ,2025年S1期
  • 【分类号】TM623
  • 【下载频次】7
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