首页> 外文期刊>Transactions of the American nuclear society >Numerical Study of the Impact of the Fuel Rod Swelling on the Thermal Hydraulics in 2X2 Rod Bundle
【24h】

Numerical Study of the Impact of the Fuel Rod Swelling on the Thermal Hydraulics in 2X2 Rod Bundle

机译:燃料棒膨胀对2X2棒束中热力学影响的数值研究

获取原文
获取原文并翻译 | 示例
           

摘要

1. According to the results of the simulations, the blockage in the flow channel caused by the cladding swelling will increase the pressure drop. If the blocked ratio is big enough, negative pressure will appear at the blocked region, which will lead to the back flow. 2. From the results in this investigation, the secondary flow intensity in the blocked region will go up and down according to the geometry of the corresponding location, the tapered section, the maximum blocked section and the divergent section. While the blocked ratio equals 60% the secondary flow intensity will decrease in fluctuation near the outlet of the blockage. Besides, whether the blockage benefits the secondary flow intensity or not is decided by the blockage ratio. 3. Based on the results of the simulations, when the blocked ratio equals to 40%, the temperature distribution is more uniform in the blocked region than that of the normal models. A blockage ratio of 60% will increase the non-uniformity of the flow field. In general, the blockage would benefit the thermal distribution downstream of the blockage region. 4. More optimized indexes are needed to evaluate the overall effect of the blockage on the thermal hydraulics of the coolant.
机译:1.根据模拟结果,由包层膨胀引起的流道阻塞将增加压降。如果阻塞率足够大,则在阻塞区域将出现负压,这将导致回流。 2.根据调查结果,阻塞区域的二次流强度将根据相应位置,锥形部分,最大阻塞部分和发散部分的几何形状而上升和下降。当阻塞率等于60%时,二次流强度将在阻塞出口附近的波动中减小。此外,堵塞是否有利于二次流动强度由堵塞率决定。 3.根据仿真结果,当阻塞率等于40%时,阻塞区域的温度分布比正常模型更均匀。 60%的堵塞率会增加流场的不均匀性。通常,阻塞将有利于阻塞区域下游的热分布。 4.需要更多优化指标来评估堵塞对冷却剂热液压的总体影响。

著录项

  • 来源
    《Transactions of the American nuclear society》 |2018年第6期|1189-1192|共4页
  • 作者

    Cen Wei; Bao-wen Yang; Bin Han;

  • 作者单位

    Science and Technology Center for Advanced Nuclear Fuel Research, School of Nuclear Science and Technology, Xi 'an Jiaotong University, Xi'an, 710049, China;

    Science and Technology Center for Advanced Nuclear Fuel Research, School of Nuclear Science and Technology, Xi 'an Jiaotong University, Xi'an, 710049, China;

    Science and Technology Center for Advanced Nuclear Fuel Research, School of Nuclear Science and Technology, Xi 'an Jiaotong University, Xi'an, 710049, China;

  • 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