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Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project

机译:主要调查结果,从经合组织/地会BSAF项目中汲取的不确定性和经验教训

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摘要

The Organisation for Economic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Station (BSAF), which started in 2012 and continued until 2018, was one of the earliest responses to the accident at Fukushima Daiichi. The project, divided into two phases, addressed the investigation of the accident at Units 1,2, and 3 by severe accident (SA) codes until 500 h, focusing on thermal hydraulics, core relocation, molten corium concrete interaction (MCCI), and fission product release and transport. The objectives of the BSAF were to make up plausible scenarios based primarily on SA forensic analysis, support the decommissioning, and inform SA code modeling. The analysis and comparison among the institutes have brought up vital insights regarding the accident progression, identifying periods of core meltdown and relocation and reactor pressure vessel (RPV) and primary containment vessel (PCV) leakage/failure through the comparison of pressure, water level, and containment atmosphere monitoring system (CAMS) signatures. The combination of code results and inspections (muon radiography, PCV inspection) has provided a picture of the current status of the debris distribution and plant status. All units present a large relocation of core materials and all of them present ex-vessel debris with Unit 1 and Unit 3 showing evidence of undergoing MCCI. Uncertainties have been identified, in particular on the time and magnitude of events such as corium relocation in the RPV and into the cavity floor and RPV and PCV rupture events. Main uncertainties resultingfrom the project are the large and continuous MCCI progression predicted by basically all the SA codes and the leak pathways from the RPV to the PCV and the PCV to the reactor building and environment. The BSAF project represents a pioneering exercise that has set the basis and provided lessons learned not only for code improvement but also for the development of new related projects to investigate in detail further aspects of the Fukushima Daiichi accident.
机译:经济合作与发展组织(经合组织)/核能署(NEA)对2012年福岛核电站(BSAF)事故的基准研究,该研究于2012年开始并持续到2018年,是最早的反应之一在福岛达奇发生事故。该项目分为两个阶段,通过严重事故(SA)代码在500小时内进行了对单位1,2和3的事故调查,重点是热液压,核心重定位,熔融冠状混凝土相互作用(MCCI),以及裂变产品释放和运输。 BSAF的目标是弥补主要基于SA法医分析的合理情景,支持退役,并通知SA代码建模。研究所之间的分析和比较对事故进展,核心熔化和搬迁和反应器压力容器(RPV)和初级容器(PCV)泄漏/失效通过压力,水位的比较来提高重要的见解,和遏制气氛监控系统(CAMS)签名。代码结果和检查(MUON X线摄影,PCV检测)的组合提供了碎片分布和工厂状态的当前状态的图片。所有单位都呈现了大量的核心材料搬迁和所有单位的所有单位与单元1和单元3所示的例子碎片显示出现在麦克西的证据。已经确定了不确定性,特别是在RPV中的叉芯和RPV和RPV和PCV破裂事件中的发生时间和大小。主要的不确定因素该项目是由基本上所有SA代码的大型和连续的MCCI进展,以及从RPV到PCV和PCV到电抗器建筑和环境的泄漏路径。 BSAF项目代表了一种开创性的练习,该练习已经设定了基础,并提供了不仅用于代码改进的经验教训,而且还用于开发新的相关项目,详细研究福岛达奇伊事故的进一步方面。

著录项

  • 来源
    《Nuclear Technology》 |2020年第9期|1449-1463|共15页
  • 作者单位

    The Institute of Applied Energy Japan;

    Centre for Energy Environment and Technology Spain;

    Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) Germany;

    Paul Scherrer Institute Division of Nuclear Energy and Safety Villigen Switzerland 5232;

    Japan Atomic Energy Agency Japan;

    Sandia National Laboratories United States;

    Sandia National Laboratories United States;

    Canadian Nuclear Laboratories Canada;

    Nuclear Safety Institute (1BRAE) Russia;

    VTT Technical Research Centre Finland;

    Institute for Radiological Protection and Nuclear Safety France;

    CEA DEN Cadarache SMTA LEAG F-13108 Saint-Paul-lez-Durance France;

    Korean Atomic Energy Research Institute Korea;

    Central Research Institute of Electrical Power Industry Japan;

    Tokyo Electric Power Company Inc. Japan;

  • 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

    OECD/NEA; BSAF project; Fukushima accident; severe accident code;

    机译:经合组织/地区;BSAF项目;福岛事故;严重事故代码;
  • 入库时间 2022-08-18 21:23:43

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