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Severe accident analysis to verify the effectiveness of severe accident management guidelines for large pressurized heavy water reactor

机译:严重事故分析,以验证大型加压重水堆严重事故管理指南的有效性

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摘要

The pressurized heavy water reactor (PHWR) contains both inherent and engineered safety features that help the reactor become resistant to severe accident and its consequences. However in case of a low frequency severe accident, despite the safety features, procedural action should be in place to mitigate the accident progression. Severe accident analysis of such low frequency event provides insight into the accident progression and basis to develop the severe accident management guidelines (SAMG). Since the order of uncertainty in the progression path of severe accident is very high, it is necessary to study the consequences of the SAMG actions prescribed. The paper discusses severe accident analysis for large PHWRs for multiple failure transients involving a high pressure scenario (initiation event like SBO with loss of emergency core cooling system and loss of moderator cooling). SAMG actions prescribed for such a scenario include water injection into steam generator, calandria vessel or calandria vault at different stages of accident. The effectiveness of SAMG actions prescribed has been investigated. It is found that there is sufficient time margin available to the operator to execute these SAMG actions and the progression of severe accident is arrested in all the three cases.
机译:加压重水反应堆(PHWR)既具有固有安全性又具有工程安全性,可帮助反应堆抵抗严重事故及其后果。但是,在发生低频严重事故的情况下,尽管具有安全功能,但仍应采取程序性措施以减轻事故的进展。对此类低频事件进行的严重事故分析可洞悉事故的进展,并为制定严重事故管理指南(SAMG)提供依据。由于严重事故发展过程中的不确定性顺序很高,因此有必要研究规定的SAMG措施的后果。本文讨论了大型PHWR的严重事故分析,涉及涉及高压场景的多次故障瞬变(诸如SBO的启动事件,包括紧急堆芯冷却系统的损失和减速​​器冷却的损失)。针对这种情况规定的SAMG措施包括在事故的不同阶段将水注入蒸汽发生器,加热炉容器或加热炉穹顶。已经对规定的SAMG行动的有效性进行了调查。发现操作员有足够的时间执行这些SAMG动作,并且在所有这三种情况下都可以阻止严重事故的发展。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2014年第10期|360-366|共7页
  • 作者单位

    Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai 400 085, India;

    Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai 400 085, India;

    Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai 400 085, India;

    Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai 400 085, India;

  • 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
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