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The effect of self-leveling on debris bed coolability under severe accident conditions

机译:在严重事故情况下自流平对碎片床可冷却性的影响

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摘要

Nordic-type boiling water reactors employ melt fragmentation, quenching, and long term cooling of the debris bed in a deep pool of water under the reactor vessel as a severe accident (SA) mitigation strategy. The height and shape of the bed are among the most important factors that determine if decay heat can be removed from the porous debris bed by natural circulation of water. The debris bed geometry depends on its formation process (melt release, fragmentation, sedimentation and settlement on the containment basemat), but it also changes with time afterwards, due to particle redistribution promoted by coolant flow (self-leveling). The ultimate goal of this work is to develop an approach to the assessment of the probability that debris in such a variable-shape bed can reach re-melting (which means failure of SA mitigation strategy), i.e. the time necessary for the slumping debris bed to reach a coolable configuration is larger than the time necessary for the debris to reach the re-melting temperature. For this purpose, previously developed models for particulate debris spreading by self-leveling and debris bed dryout are combined to assess the time necessary to reach a coolable state and evaluate its uncertainty. Sensitivity analysis was performed to screen out less important input parameters, after which Monte Carlo simulation was carried out in order to collect statistical characteristics of the coolability time. The obtained results suggest that, given the parameters ranges typical of Nordic BWR5, only a small fraction of debris beds configurations exhibits the occurrence of dryout. Of the initially non-coolable configurations, a significant portion becomes coolable due to debris bed self-leveling. (C) 2016 Elsevier B.V. All rights reserved.
机译:北欧型沸水反应堆采用熔体破碎,淬火和长期冷却反应堆容器下方深水池中的碎屑床作为严重事故(SA)缓解策略。床的高度和形状是决定是否可以通过自然水循环从多孔碎屑床中去除腐烂热量的最重要因素。碎屑床的几何形状取决于其形成过程(融化释放,破碎,沉降和在安全壳底垫上的沉降),但是由于冷却剂流动(自流平)促进了颗粒的重新分布,碎屑床的形状也会随时间而改变。这项工作的最终目标是开发一种方法来评估这种可变形状床中的碎屑达到重新熔化的可能性(这意味着SA缓解策略失败),即塌陷碎屑床所需的时间。达到可冷却配置的时间要大于碎片达到重熔温度所需的时间。为此,结合了以前开发的通过自动找平和碎屑床变干进行的碎屑散布模型,以评估达到可冷却状态所需的时间并评估其不确定性。进行敏感性分析以筛选不太重要的输入参数,然后进行蒙特卡洛模拟,以收集可冷却时间的统计特征。获得的结果表明,给定Nordic BWR5的典型参数范围,只有一小部分的碎屑床结构会出现变干的情况。在最初不可冷却的配置中,很大一部分由于碎屑床的自流平而变得可冷却。 (C)2016 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2016年第8期|246-259|共14页
  • 作者单位

    Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, Sweden;

    Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, Sweden;

    Russian Acad Sci, Inst Problems Mech, Ave Vernadskogo 101 Bldg 1, Moscow 119526, Russia;

    Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, Sweden;

  • 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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  • 入库时间 2022-08-18 00:41:52

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