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MELCOR modeling and sensitivity analysis of Fukushima Daiichi unit 2 accident considering the latest TEPCO investigations

机译:考虑到最新的东京电力公司调查,福岛第一核电站2号事故的MELCOR建模和敏感性分析

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摘要

Fukushima Daiichi accident occurred on 11 March 2011 due to the Great East japan Earthquake and the following tsunami. Recently, Tokyo Electric Power Company (TEPCO) published investigation reports pertaining to the status of unit 2 and other issues that were confirmed. The present study modeled unit 2 accident with MELCOR 2.1 code and performed sensitivity analysis, in order to provide information towards understanding severe accident. The two-phase flow rate and its void fraction in the steam line connecting to the turbine of reactor core isolation cooling (RCIC) system were calculated using the developed RCIC operation model, and the pump injection rate was obtained as well. The suppression chamber (S/C) was divided into three layers with flow path connection to model thermal stratification and the mixing flow at SRV discharge, thereby enabling to capture the measured dry well (D/W) pressure. Through sensitivity analysis of seawater injection, it indicates that the likely seawater injection rate was about 1-2% of the total flow rate through fire engines, and the corresponding reactor pressure vessel (RPV) lower head failure time was located in 92.84 h- 96.17 h. As a result, about 74% of total fuel debris discharged into the reactor pedestal, and the release fractions of noble gas, iodine and cesium to the environment were about 0.741, 0.0167 and 0.00331, respectively. Even though the plausible accident progression was tentatively given, there are still many uncertainties concerning models, boundary conditions and the accident progression. (C) 2017 Elsevier Ltd. All rights reserved.
机译:由于东日本大地震和随后的海啸,2011年3月11日发生了福岛第一核电站事故。最近,东京电力公司(TEPCO)发布了有关2号机组状态和其他已确认问题的调查报告。本研究使用MELCOR 2.1代码对2号机组事故进行了建模,并进行了敏感性分析,以便为了解严重事故提供信息。使用开发的RCIC运行模型,计算了连接到反应堆堆芯隔离冷却(RCIC)系统的涡轮机的蒸汽管线中的两相流速及其空隙率,并获得了泵的喷射率。抑制室(S / C)通过流路连接分为三层,以模拟热分层和SRV排放时的混合流,从而能够捕获测得的干井(D / W)压力。通过海水注入的敏感性分析,表明可能的海水注入率约为消防车总流量的1-2%,相应的反应堆压力容器(RPV)的下水头故障时间位于92.84 h- 96.17。 H。结果,约有74%的总燃料碎片排入反应器基座,稀有气体,碘和铯向环境的释放率分别约为0.741、0.0167和0.00331。即使初步给出了合理的事故进展,但在模型,边界条件和事故进展方面仍然存在许多不确定性。 (C)2017 Elsevier Ltd.保留所有权利。

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  • 来源
    《Annals of nuclear energy》 |2018年第2期|364-373|共10页
  • 作者单位

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

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

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

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

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

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Fukushima; Severe accident; Sensitivity analysis; MELCOR;

    机译:福岛;严重事故;敏感性分析;MELCOR;

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