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Sensitivity analysis of core slumping and debris quenching behavior of Fukushima Daiichi Unit-3 accident

机译:福岛Daiichi单元-3意外核心坍塌和碎片淬火行为的敏感性分析

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摘要

The Great East Japan earthquake and the subsequent tsunami which occurred on March 11th, 2011 put the operating Units 1-3 at Fukushima Daiichi Nuclear Power Plant (NPP) in severe accident conditions and core meltdown due to station blackout. Although research efforts have been made by various parties to study the accident scenarios since the Fukushima accident, there remain unresolved issues regarding the core degradation behavior suggested by measurement data such as water level, Reactor Pressure Vessel (RPV) pressure and Primary Containment Vessel (PCV) pressure. To analyze and resolve such issues would be helpful to promote further understanding of the severe accident scenario at Fukushima units as well as the decommissioning work undergoing.The current study focuses on a detailed analysis of the RPV pressure peak event that occurred in Unit-3 at 12:00 on March 13th 2011. Sensitivity analysis cases were carried out with MELCOR 2.2 code' with sensitivity parameters that can influence the RPV pressure behavior, such as the debris quenching heat transfer coefficient, the number of opening SRVs during the RPV pressure peak event, amount of core slumping and particulate debris diameter. The cases that could reproduce the RPV pressure peak were further discussed to show likely debris bed energy history and the water mass history in the lower plenum during the RPV pressure peak event. The current study suggests that 1) Opening of SRVs equivalent to the total area of 4-6 fully-open SRVs (or equivalent leak area) could have occurred during the pressurization phase of the RPV accompanied by heavy debris quenching effect, while the opening of SRVs equivalent to a total area of at least 2 fully-open SRVs (or equivalent leak area) could have occurred during the depressurization phase of the RPV accompanied by moderate debris quenching effect. 2) The particulate debris diameter is not a very sensitive parameter when evaluating the debris quenching effect of Unit-3 in the current MELCOR modeling. 3) The current modeling suggests that around 70-110 GJ of energy can be removed by coolant during the debris quenching period with 30 tons of water reduction from the lower plenum. (C) 2020 Elsevier Ltd. All rights reserved.
机译:大东日本地震和2011年3月11日发生的随后的海啸在福岛达奇核电站(NPP)在严重事故条件下,由于站停电,核心事故条件和核心崩溃的运行单位为1-3。虽然各方都是通过福岛事故来研究事故情景的研究努力,但仍然存在关于水位,反应器压力容器(RPV)压力和主要容器(PCV ) 压力。分析和解决这些问题将有助于促进对福岛单位的严重事故情景以及接受的退役工作。目前的研究重点是对单位-3发生的RPV压力峰事件的详细分析12:00 2011年3月13日。敏感性分析案例与熔体2.2码'进行,具有敏感性参数,可以影响RPV压力行为,例如碎片淬火传热系数,在RPV压力峰事件期间打开SRV的数量,核心坍塌和颗粒碎片直径的量。进一步讨论了可以再现RPV压力峰值的病例,以显示在RPV压力峰值事件期间,在下层的可能碎片床能量历史和水质历史。目前的研究表明,在RPV的加压阶段伴随着重型碎片淬火效果,可以在RPV的加压阶段期间发生相当于4-6完全开放的SRV(或等效泄漏面积)的总面积的SRV的开度。在RPV的减压阶段伴随着中度碎片淬火效果,可以发生相当于至少2个完全打开的SRV(或等效泄漏区域)的总面积的SRV。 2)当在当前熔体建模中评估单元-3的碎屑淬火效果时,颗粒碎片直径不是非常敏感的参数。 3)目前的建模表明,在碎屑淬火时段期间,可以通过冷却剂从碎屑淬火周期中除去大约70-110GJ的能量,从而从下部增压室减少30吨。 (c)2020 elestvier有限公司保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2021年第1期|107819.1-107819.10|共10页
  • 作者单位

    Japan Atom Energy Agcy Oarai Res & Dev Inst 4002 Narita Cho Oarai Ibaraki 3111393 Japan|Waseda Univ Grad Sch Adv Sci & Engn Shinjuku Ku Bldg 51 Nishi Waseda Campus 3-4-1 Okubo Tokyo 1698555 Japan;

    Japan Atom Energy Agcy Oarai Res & Dev Inst 4002 Narita Cho Oarai Ibaraki 3111393 Japan;

    Waseda Univ Grad Sch Adv Sci & Engn Shinjuku Ku Bldg 51 Nishi Waseda Campus 3-4-1 Okubo Tokyo 1698555 Japan;

    Waseda Univ Grad Sch Adv Sci & Engn Shinjuku Ku Bldg 51 Nishi Waseda Campus 3-4-1 Okubo Tokyo 1698555 Japan;

    Univ Wisconsin Dept Engn Phys 1500 Engn Dr Madison WI 53706 USA;

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

    Fukushima Daichi Nuclear Power PLant; Severe accident; BWR; Sensitivity analysis;

    机译:Fukusima Daiichi核电站;严重事故;BWR;敏感性分析;

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