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A REASSESSMENT OF LOW PROBABILITY CONTAINMENT FAILURE MODES AND PHENOMENA IN A LONG-TERM STATION BLACKOUT

机译:长期停电时低概率保持故障模式和现象的重新评估

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摘要

The risk-dominant containment failure modes of a pressurized water reactor are reassessed using the current state of knowledge for the phenomena that contribute to these failure modes. Our review concludes that some mechanisms that were considered as having the potential to result in containment failure at the time of NUREG-1150, such as in-vessel steam explosions and vessel launch (i.e., the alpha-mode containment failure), have subsequently undergone sufficient review and can be excluded from further consideration. For other phenomena, such as high-pressure melt ejection (HPME) and combustible gas explosions, our review concludes that substantial uncertainties still exist with regard to modeling in system level codes; for combustion events, careful consideration is still required when making severe accident management decisions. With regard to HPME, sensitivity studies have been performed with the MELCOR computer code to address the effects of modeling uncertainties on containment loading. Sensitivity studies using MELCOR have also been performed with regard to combustion events to examine gas generation, the effect of containment cooling on the potential for deflagrations, and the combustion load on containment. Combustion loads are compared to the NUREG-1150 containment fragility curve to assess the likelihood of containment failure. Our MELCOR analyses agree with the NUREG-1150 assumption that insufficient hydrogen is generated in-vessel to result in containment failure. Sensitivity studies regarding the rate and timing of reflooding a degraded core do not indicate a significant effect on hydrogen production in-vessel or a significant challenge to containment integrity regarding HPME. However, it is observed that recovery actions resulting in cooling of the containment atmosphere could result in deinerting the containment and lead to a sufficiently energetic combustion event that can fail the containment.
机译:使用导致这些故障模式的现象的当前知识状态,重新评估压水堆的风险主导型安全壳故障模式。我们的审查得出的结论是,一些在NUREG-1150时代被认为有可能导致密闭失效的机制,例如船内蒸汽爆炸和船舶下水(即,α模式密闭失效),随后发生了足够的审查,可以从进一步考虑中排除。对于其他现象,例如高压熔体喷射(HPME)和可燃气体爆炸,我们的评论得出结论,在系统级代码的建模方面仍然存在很大的不确定性。对于燃烧事件,在制定严格的事故管理决策时仍需要仔细考虑。关于HPME,已经使用MELCOR计算机代码进行了敏感性研究,以解决建模不确定性对安全壳载荷的影响。还使用MELCOR对燃烧事件进行了敏感性研究,以检查气体的产生,安全壳冷却对爆燃可能性的影响以及对安全壳的燃烧负荷。将燃烧负荷与NUREG-1150安全壳脆性曲线进行比较,以评估安全壳失效的可能性。我们的MELCOR分析与NUREG-1150假设一致,即容器中生成的氢气不足以导致安全壳失效。关于再降解核芯的速度和时间的敏感性研究并未显示出对氢气生产的显着影响或对HPME的密闭性的重大挑战。但是,观察到,导致安全壳气氛冷却的恢复动作可能导致安全壳失效,并导致足以使安全壳失效的高能燃烧事件。

著录项

  • 来源
    《Nuclear Technology》 |2014年第2期|198-215|共18页
  • 作者单位

    The Ohio State University, 201 West 19th Avenue, Columbus, Ohio 43210;

    The Ohio State University, 201 West 19th Avenue, Columbus, Ohio 43210;

    The Ohio State University, 201 West 19th Avenue, Columbus, Ohio 43210;

  • 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
  • 关键词

    combustible gas generation; containment failure; deflagrations;

    机译:可燃气体的产生;收容失败;爆燃;
  • 入库时间 2022-08-18 00:43:13

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