...
首页> 外文期刊>Nuclear Engineering and Design >Study of debris-generated core blockage scenarios during loss of coolant accidents using RELAP5-3D
【24h】

Study of debris-generated core blockage scenarios during loss of coolant accidents using RELAP5-3D

机译:使用RELAP5-3D研究在冷却液损失事故中碎片产生的堆芯堵塞情况

获取原文
获取原文并翻译 | 示例
           

摘要

Two RELAP5-3D models of a typical four-loop pressurized water reactor were prepared to simulate the reactor system response during loss of coolant accident (LOCA) scenarios of different break sizes and locations, under hypothesized debris-generated core blockage conditions. Three break sizes consisting of 2-in., 6-in., and double-ended guillotine (DEG) were selected as representative cases for small, medium and large break sizes, respectively. Simulations were performed to analyze the behavior of the system during a cold leg break and a hot leg break, assuming that all safety systems were available during the phases of the accident. A simpler model was used to perform the simulations up to the long-term cooling phase of the accident, under a full core and core bypass blockage condition. The simulation results help in identifying critical scenarios which, under such circumstances, may lead to core damage. One critical scenario was selected and analyzed with a more detailed core nodalization using RELAP5-3D multi-dimensional components, under different core blockage schemes, including partial core blockage, showing the ability of the cooling water to remove the decay heat from the core under such conditions.
机译:准备了两个典型的四回路加压水反应堆的RELAP5-3D模型,以在假定的碎屑产生的堆芯堵塞条件下,模拟在不同断裂尺寸和位置的冷却剂事故(LOCA)损失情况下,模拟反应堆系统的响应。对于小,中和大断头尺寸,分别选择了由2英寸,6英寸和双头断头台(DEG)组成的三种断头尺寸。假设在事故发生期间所有安全系统均可用,则进行了仿真以分析系统在冷腿和热腿休息期间的行为。在完全堆芯和堆芯旁路阻塞的情况下,使用了一个更简单的模型来进行模拟,直到事故的长期冷却阶段。仿真结果有助于识别在这种情况下可能导致核心损坏的关键情况。选择了一个关键方案,并在不同的堆芯堵塞方案(包括部分堆芯堵塞)下,使用RELAP5-3D多维组件对堆芯进行了更详细的节点化分析,显示了在这种情况下冷却水从堆芯中去除衰变热的能力。条件。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2013年第8期|144-155|共12页
  • 作者单位

    Department of Nuclear Engineering, Texas A&M University, College Station, TX 77843-3133, USA;

    Department of Nuclear Engineering, Texas A&M University, College Station, TX 77843-3133, USA;

  • 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

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