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首页> 外文期刊>Progress in Nuclear Energy >Comparative analysis of auxiliary feedwater system and passive safety system under typical accident scenarios for integrated pressurized water reactor (IPWR)
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Comparative analysis of auxiliary feedwater system and passive safety system under typical accident scenarios for integrated pressurized water reactor (IPWR)

机译：集成压水堆（IPWR）典型事故场景下辅助给水系统和被动安全系统的比较分析

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摘要

The Integrated Pressurized Water Reactor (IPWR) designed with series of passive safety system has been regarded as a very promising reactor concept. In this paper, in order to assess the accident mitigation ability of passive safety systems in China 100 MW IPWR, the complete system models, including the reactor vessel, passive safety injection system and passive residual heat removal system, were established using RELAP5 software. The comprehensive and quantitative comparative analysis of auxiliary feed water system and passive safety system under typical accident scenarios, including loss of flow accident and Station Black-out (SBO), were investigated, respectively. Results show that the passive residual heat removal system has the similar accident mitigation capability compared with the auxiliary feed water system, which is adopted in most of traditional PWR design. And the IPWR could realize the reactor safe shutdown under typical accident scenarios with passive safety systems. Finally, the Small break loss of coolant accident (SBLOCA) induced by pressurizer surge line rupture was calculated to verify the function of passive safety systems for IPWR. Results demonstrate that the passive safety system could provide emergency coolant to the reactor and remove the reactor decay heat successfully. This work is meaningful for the quantitative evaluation of passive safety systems in IPWR.
机译：设计有一系列被动安全系统的集成压水堆（IPWR）被认为是非常有前途的反应堆概念。为了评估中国100 MW IPWR被动安全系统的事故缓解能力，使用RELAP5软件建立了反应堆容器，被动安全注入系统和被动余热去除系统的完整系统模型。研究了典型事故情景下的辅助给水系统和被动安全系统的综合定量比较分析，包括失水事故和车站停电事故。结果表明，被动余热排除系统与辅助给水系统相比具有相似的事故缓解能力，而传统的压水堆设计大多采用了辅助给水系统。 IPWR可以通过被动安全系统在典型事故情况下实现反应堆的安全关闭。最后，计算了由增压器喘振管线破裂引起的冷却液小断裂损失事故（SBLOCA），以验证IPWR被动安全系统的功能。结果表明，被动安全系统可以为反应堆提供应急冷却剂，并成功消除反应堆的衰减热量。这项工作对于IPWR中被动安全系统的定量评估具有重要意义。

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  • 来源
    《Progress in Nuclear Energy》 |2019年第8期|42-51|共10页
  • 作者

    Hou Yandong; Wang Mingjun; Zhang Jing; Qiu Suizheng; Su G. H.; Tian Wenxi;

  • 作者单位

    Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Shaanxi, Peoples R China;

    Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Shaanxi, Peoples R China;

    Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Shaanxi, Peoples R China;

    Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Shaanxi, Peoples R China;

    Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Shaanxi, Peoples R China;

    Xi An Jiao Tong Univ, Dept Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Xian 710049, Shaanxi, Peoples R China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    IPWR; Auxiliary feed water system; Passive safety system; Accident analysis;

    机译：IPWR;辅助给水系统;被动安全系统;事故分析;

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