首页> 外文期刊>Nuclear Technology >State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analyses for Station Blackout Scenarios
【24h】

State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analyses for Station Blackout Scenarios

机译:最先进的反应堆后果分析项目:站立停电方案的不确定性分析

获取原文
获取原文并翻译 | 示例
           

摘要

This paper provides an overview of the U.S. Nuclear Regulatory Commission's (NRC's) project to develop a technical report summarizing the most important insights from its three State-of-the-Art Reactor Consequence Analyses (SOARCA) project uncertainty analyses (UAs). The NRC, with Sandia National Laboratories, has completed three UAs as part of the SOARCA project, for three different operating reactor types in three different locations in the United States. The SOARCA UAs included an integrated evaluation ofuncertainty in accident progression, radiological release, and off-site health consequence projections. These three UAs are currently documented in three detailed reports. The NRC is currently developing a technical overview report summarizing the important insights from the three SOARCA UAs. The purpose of the NRC summary is to provide a useful reference for regulatory applications that require the evaluation of off-site consequence risk from beyond-design-basis-event severe accidents. Examples include regulatory and cost-benefit analyses that rely on off-site consequence projections using the MELCOR Accident Consequence Code System (MACCS) code, in conjunction with MELCOR for source term characterization. This paper provides an overview and discusses the overall scope and methodology of the SOARCA UAs and the approach for the summary report currently under development.
机译:本文提供了美国核管理委员会(NRC的)项目的概述开发的技术报告从三个国家的最先进反应堆后果分析(SOARCA)项目的不确定性分析(UAS)总结了最重要的见解。核管理委员会,与桑迪亚国家实验室,已完成3周的UA作为SOARCA项目的一部分,在美国三个不同的地点三种不同的工作堆型。该SOARCA的UA包括在事故发展的综合评价ofuncertainty,放射性的释放,和场外的健康后果的预测。目前这三种无人机系统记录的三个详细的报告。核管理委员会目前正在开发的技术概述总结报告从三个SOARCA的UA的重要见解。 NRC的摘要的目的是为那些需要从超越,设计基准事件严重事故场外后果的风险评估监管应用提供有益的参考。例子包括依赖于使用MELCOR事故后果代码系统(MACCS)代码,连同MELCOR为源项特征异地后果预测的监管和成本效益分析。本文提供了一个概述,并讨论整体范围和SOARCA的UA的方法和目前正在开发总结报告的办法。

著录项

  • 来源
    《Nuclear Technology》 |2021年第3期|441-451|共11页
  • 作者单位

    U.S. Nuclear Regulatory Commission Washingon District of Columbia 20555;

    U.S. Nuclear Regulatory Commission Washingon District of Columbia 20555;

    U.S. Nuclear Regulatory Commission Washingon District of Columbia 20555;

    Sandia National Laboratories Albuquerque New Mexico 87185;

    Sandia National Laboratories Albuquerque New Mexico 87185;

    Sandia National Laboratories Albuquerque New Mexico 87185;

    Sandia National Laboratories Albuquerque New Mexico 87185;

    Sandia National Laboratories Albuquerque New Mexico 87185;

    Sandia National Laboratories Albuquerque New Mexico 87185;

  • 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

    Severe accident consequences; uncertainty analysis;

    机译:严重事故后果;不确定性分析;

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