...
首页> 外文期刊>Annals of nuclear energy >Re-assessment of station blackout accident in WER-1000 NPP with additional measures following Fukushima accident using Relap/Mod3.2
【24h】

Re-assessment of station blackout accident in WER-1000 NPP with additional measures following Fukushima accident using Relap/Mod3.2

机译:使用Relap / Mod3.2对WER-1000 NPP的车站停电事故进行重新评估,并采取福岛事故后的附加措施

获取原文
获取原文并翻译 | 示例
           

摘要

The Fukushima accident indicated that the safety systems of nuclear power plants should be re-assessed against site-specific extreme natural hazards using additional BDBA management equipment and organizational measures. The occurrence of loss of power supply (SBO) accident in VVER-1000 NPP, which is the most contributor to the total core damage frequency, is the focus of this study. The SBO accident analysis of the reference plant with and without operator actions are investigated by Relap5 code to identify the characteristics of additional measures, available times for operator actions (critical time points) as well as scenarios to manage the accident consequences. The additional BDBA management equipment includes robust and reliable portable additional electrical power backup sources and water supplies into the primary and secondary cooling system to remove the residual heat of the core. The main purpose of this study is an evaluation of efficiency and sufficiency of additional equipment and organizational measures at NPP site based on deterministic safety analysis during SBO accident. This analysis is also expected to prepare a useful guideline for the SBO management in VVER-1000/V-446 NPP. A validated Relap5 model of VVER-1000 is employed to implement the proposed SBO accident scenarios consisting of residual heat removal through primary and secondary cooling systems as well as additional measures to mitigate this accident. The main thermal-hydraulic parameters of NPP in response to SBO accident are compared with specified acceptance criteria. The deterministic safety analysis demonstrates the provided accident scenarios with specified additional BDBA management equipment ensures the long-term reliable cooling of the reactor core under loss of power supply condition. The result also illustrates that a high degree of confidence in the robustness of the VVER-1000 NPP could be achieved against SBO accident with the inclusion of additional measures. (C) 2019 Elsevier Ltd. All rights reserved.
机译:福岛事故表明,应使用附加的BDBA管理设备和组织措施,针对特定场所的极端自然灾害对核电厂的安全系统进行重新评估。 VVER-1000 NPP中的电源丢失(SBO)事故的发生是最主要的核心损坏频率,是本研究的重点。通过Relap5代码对具有和不具有操作员动作的参考工厂的SBO事故分析进行调查,以识别其他措施的特征,操作员动作的可用时间(关键时间点)以及管理事故后果的方案。附加的BDBA管理设备包括功能强大且可靠的便携式附加电源备用电源,以及将水供应到主冷却系统和辅助冷却系统中,以消除堆芯的余热。这项研究的主要目的是基于SBO事故期间的确定性安全分析,对NPP现场附加设备和组织措施的效率和充分性进行评估。该分析也有望为VVER-1000 / V-446 NPP中的SBO管理准备有用的指南。采用经过验证的VVER-1000 Relap5模型来实施建议的SBO事故场景,包括通过一次和二次冷却系统清除余热以及减轻该事故的其他措施。将应对SBO事故的NPP的主要热工液压参数与指定的验收标准进行比较。确定性安全分析表明,使用指定的附加BDBA管理设备提供的事故情况可确保在断电情况下对反应堆堆芯进行长期可靠的冷却。该结果还表明,通过采用其他措施,可以对SVER事故对VVER-1000 NPP的坚固性有高度的信心。 (C)2019 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2019年第7期|316-330|共15页
  • 作者单位

    Shiraz Univ, Dept Nucl Engn, Shiraz 7193616548, Iran|Shiraz Univ, Nucl Safety Res Ctr, Shiraz 7193616548, Iran;

    Shiraz Univ, Dept Nucl Engn, Shiraz 7193616548, Iran|Shiraz Univ, Nucl Safety Res Ctr, Shiraz 7193616548, Iran;

    Shiraz Univ, Dept Nucl Engn, Shiraz 7193616548, Iran|Shiraz Univ, Nucl Safety Res Ctr, Shiraz 7193616548, Iran;

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

    Fukushima accident; SBO; Additional measures; DSA; Relap5/Mod3.2;

    机译:福岛事故;SBO;附加措施;DSA;Relap5 / Mod3.2;

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号