首页> 外文期刊>Annals of nuclear energy >Experimental study on the blowdown load during the steam generator feedwater line break accident in the evolutionary pressurized water reactor
【24h】

Experimental study on the blowdown load during the steam generator feedwater line break accident in the evolutionary pressurized water reactor

机译:演化压水堆蒸汽发生器给水管道断裂事故排污负荷的试验研究。

获取原文
获取原文并翻译 | 示例
           

摘要

Integral effect tests using the ATLAS facility were performed to obtain the thermal-hydraulic parameters such as dynamic and static pressures, local temperatures, and flow rates during a feedwater line break of a steam generator. The break of a feedwater line was simulated using a double rupture disc assembly in order to satisfy the requirements for the break opening time of around a few milliseconds. In the present study, estimated break opening time was less than 1.5 ms and broken areas were 48.1% and 93.4% of the feedwater line, respectively. The maximum dynamic pressures of about 1.57 bar were obtained inside of feedwater box that was closest to the break location of the feedwater line. After the break of the feed-water line, propagation of the pressure wave along the distance from the break location inside the steam generator was clearly and pertinently observed in all the tests. From a structural integrity point of view, however, the risk induced by this maximum dynamic load could be treated to be insignificant. Based on the present experimental data, an analysis was performed using the best-estimate thermal-hydraulic system code, MARS 3,1 with an aim of qualitatively validating the test results and also evaluating the blowdown load prediction capability of the best-estimate system code in the simulation of steam generator feedwater line break. Calculation results on overall trends of the dynamic pressure behavior are comparable with the test results which indicate the feasibility of dynamic load prediction using the MARS code. As the break opening time became shorter and the broken area became larger, the dynamic pressures were calculated to be significant values in the sensitivity analyzes. 【keyworks】Integral effect test;Double rupture disc assembly;Feedwater line break;Blowdown load
机译:使用ATLAS设施进行了整体效果测试,以获取热工液压参数,例如蒸汽发生器给水管线中断期间的动态和静态压力,局部温度和流速。为了满足大约几毫秒的中断打开时间的要求,使用双破裂盘组件模拟了给水管线的中断。在本研究中,估计的破裂打开时间小于1.5 ms,破裂面积分别占给水管线的48.1%和93.4%。在最靠近给水管线中断位置的给水箱内获得了约1.57 bar的最大动压。给水管线断裂后,在所有测试中均清晰,有针对性地观察到压力波沿距蒸汽发生器内部断裂位置的距离传播。但是,从结构完整性的角度来看,可以将这种最大动态载荷所引起的风险视为无关紧要。根据目前的实验数据,使用最佳估计的液压系统代码MARS 3,1进行分析,以定性验证测试结果并评估最佳估计的系统代码的排污负荷预测能力在模拟蒸汽发生器给水管线的断裂处。动态压力行为总体趋势的计算结果与测试结果相当,表明使用MARS代码进行动态载荷预测的可行性。随着开裂时间变短和破损面积变大,动压被计算为敏感度分析中的重要值。 【主要工作】整体效果测试;双爆破片组装;给水断线;排污负荷

著录项

  • 来源
    《Annals of nuclear energy》 |2011年第5期|p.953-963|共11页
  • 作者单位

    Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea;

    Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea;

    Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea;

    Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea;

    Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea;

    Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea;

    Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea;

    Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea;

    Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea;

    DOOSAN Heavy Industries and Construction Co., Ltd., Republic of Korea;

  • 收录信息
  • 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