首页> 外文期刊>Nuclear Technology >ANALYSIS OF ACCIDENT PROGRESSION WITH THE SAMPSON CODE IN FUKUSHIMA DAIICHI NUCLEAR POWER PLANT UNIT 2
【24h】

ANALYSIS OF ACCIDENT PROGRESSION WITH THE SAMPSON CODE IN FUKUSHIMA DAIICHI NUCLEAR POWER PLANT UNIT 2

机译:福岛大地核电站2号机组使用桑普森码进行事故分析

获取原文
获取原文并翻译 | 示例
       

摘要

The Great East Japan Earthquake and tsunami on March 11, 2011, mark the start of the nuclear accident at the Fukushima Daiichi nuclear power plant. Progression of the accident has been analyzed with the SAMPSON code. SAMPSON was originally designed as a large-scale simulation system with the maximum use of mechanistic models and theoretically based equations. In the progression analysis done for Unit 2, SAMPSON could reproduce the pressure transient of the reactor pressure vessel (RPV) reasonably well by assuming partial load operation of the reactor core isolation cooling system (RCIC). The pressure transient of the primary containment vessel was reproduced reasonably well by assuming torus room flooding. After the RCIC trip and manual opening of the steam relief valve, SAMPSON predicted the damage to the upper part of the fuel assemblies near the core center and RPV failure due to creep rupture. More than 91 wt% of the core debris relocated to the lower plenum was as particles, and the major constituents were UO_2, Zr, and ZrO_2 by SAMPSON analysis.
机译:2011年3月11日发生的东日本大地震和海啸标志着福岛第一核电站发生核事故。已使用SAMPSON代码分析了事故的进展。 SAMPSON最初被设计为大型仿真系统,其中充分利用了机械模型和基于理论的方程式。在对2号机组进行的进度分析中,桑普森通过假设反应堆堆芯隔离冷却系统(RCIC)处于部分负荷运行,可以相当好地再现反应堆压力容器(RPV)的压力瞬变。通过假定环形室浸水,可以很好地再现主安全壳的压力瞬变。在RCIC跳闸和手动打开蒸汽溢流阀后,SAMPSON预测了燃料组件上部在核心中心附近的损坏以及RPV因蠕变破裂而失效。通过SAMPSON分析,超过91 wt%的重心碎片以颗粒的形式迁移到下气室,主要成分为UO_2,Zr和ZrO_2。

著录项

  • 来源
    《Nuclear Technology》 |2014年第2期|255-262|共8页
  • 作者单位

    Institute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 Japan;

    Institute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 Japan;

    Institute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 Japan;

    Institute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 Japan;

    Institute of Applied Energy, 14-2 Nishi-Shimbashi 1-Chome, Minato-ku, Tokyo, 105-0003 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

    severe nuclear accidents; fuel relocation; mechanistic model;

    机译:严重的核事故;燃料调动;机械模型;
  • 入库时间 2022-08-18 00:43:13

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