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Thermal-hydraulic analysis on the effect of operator action in the loss of shutdown cooling system accident in a PWR

机译:热工水力分析对压水堆中关闭冷却系统事故中操作员动作的影响

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摘要

It is necessary to develop PSA methodology and integrated accident management technology during low power/shutdown operations. To develop this technology, thermal-hydraulic analysis is necessarily required to access the trend of plant process parameters and operator's grace time after initiation of the accident. In this study, the thermal-hydraulic behavior in the loss of shutdown cooling system accident during low power/shutdown operations at the Korean standard nuclear power plant was analyzed using the best-estimate thermal-hydraulic analysis code, MARS2.1. The effects of operator's action and initiation of accident mitigation system, such as safety injection and gravity feed on mitigation of the accident during shutdown operations are also analyzed.rnWhen steam generators are unavailable or vent paths with large cross-sectional area are open in the accident, the core damage occurs earlier than the cases of steam generators available or vent paths with small cross-sectional area. If an operator takes an action to mitigate the accident, the accident can be mitigated considerably. To mitigate the accident, high-pressure safety injection is more effective in POS4B and gravity feed is more effective in POS5. The results of this study can contribute to the plant safety improvement because those can provide the time for an operator to take an action to mitigate the accident by providing quantitative time of core damage. The results of this study can also provide information in developing operating procedure and accident management technology.
机译:在低功率/停机操作期间,有必要开发PSA方法和集成的事故管理技术。为了开发该技术,必须进行热工液压分析,以获取事故发生后工厂过程参数的趋势和操作员的宽限时间。在这项研究中,使用最佳估计的热工水力分析代码MARS2.1分析了韩国标准核电站在低功率/停机运行过程中停机冷却系统事故损失中的热工行为。还分析了操作员的行动和事故缓解系统的启动(例如安全注入和重力给料)对停机过程中缓解事故的影响.rn当蒸汽发生器不可用或大横截面的排气路径打开时,芯子损坏发生的时间要早​​于可用的蒸汽发生器或横截面面积小的通风道。如果操作员采取减轻事故的措施,则可以大大减轻事故的发生。为了减轻事故的发生,高压安全注射在POS4B中更有效,重力进料在POS5中更有效。这项研究的结果可以为工厂安全性改善做出贡献,因为这些结果可以为操作员提供时间,以通过提供定量的核心损坏时间来采取措施减轻事故的发生。这项研究的结果还可以为开发操作程序和事故管理技术提供信息。

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  • 来源
    《Nuclear Engineering and Design》 |2007年第19期|2054-2063|共10页
  • 作者

    Young-Seok Son; Jee-Young Shin;

  • 作者单位

    Department of Mechanical Engineering, Dong-Eui University, 995 Eomgwangno, Busanjin-Gu, Busan 614-714, South Korea;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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