首页> 外文学位 >文献详情
【24h】

Subcooled choked flow through steam generator tube cracks.

机译:过冷的tube流通过蒸汽发生器的管子破裂。

获取原文
获取原文并翻译 | 示例

摘要

The work presented here describes an experimental investigation into the choked flow of initially subcooled water through simulated steam generator tube cracks at pressures up to 6.9 MPa. The study of such flow is relevant to the prediction of leak flow rates from a nuclear reactor primary side to secondary side through cracks in steam generator tubes. An experimental approach to measuring such flow is de- scribed. Experimental results from data found in literature as well as the data collected in this work are compared with predictions from presented models as well as predictions from the thermal-hydraulic system code RELAP5. It is found that the homogeneous equilibrium model underpredicts choked flow rates of subcooled water through slits and artificial steam generator tube cracks. Additional modeling of thermal non-equilibrium improves the predictibility of choking mass flux for homogeneous models, however they fail to account for the characteristics of the two-phase pressure drop. An integral modeling approach is enhanced using a correlation developed from the data herein. Also, an assessment of the thermal-hydraulics code RELAP5 is performed and it’s applicability to predict choking flow rates through steam generator tube cracks is addressed. This assessment determined that the Henry & Fauske model, as coded in RELAP5, is best suited for modeling choked flow through steam generator tube cracks. Finally, an approach to applying choked flow data that is not at the same thermo-dynamic conditions as a prototype is developed.
机译:此处介绍的工作描述了对初始过冷水在压力高达6.9 MPa时通过模拟蒸汽发生器管子的the流的实验研究。这种流动的研究与通过蒸汽发生器管中的裂纹从核反应堆一次侧到二次侧的泄漏流量的预测有关。描述了一种测量这种流量的实验方法。来自文献中的数据以及这项工作中收集的数据的实验结果与现有模型的预测以及热液系统代码RELAP5的预测进行了比较。发现均质平衡模型低估了过冷水通过缝隙和人工蒸汽发生器管裂纹的阻塞流量。对于非均热模型,附加的热非平衡模型可以提高节流质量通量的可预测性,但是它们无法解决两相压降的特征。使用根据本文数据开发的相关性,可以增强整体建模方法。此外,还对热工液压代码RELAP5进行了评估,并解决了预测通过蒸汽发生器管裂纹的窒息流量的适用性。该评估确定,RELAP5中编码的Henry&Fauske模型最适合于模拟通过蒸汽发生器管道裂缝的crack流。最后,开发了一种方法来应用与原型不同的热力学条件下的节流数据。

著录项

  • 作者

    Wolf, Brian J.;

  • 作者单位

    Purdue University.;

  • 授予单位 Purdue University.;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2012
  • 页码 211 p.
  • 总页数 211
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

  • 入库时间 2022-08-17 11:42:48

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