...
首页> 外文期刊>Nuclear Engineering and Design >An experimental investigation on the critical heat flux enhancement by mechanical vibration in vertical round tube
【24h】

An experimental investigation on the critical heat flux enhancement by mechanical vibration in vertical round tube

机译:立式圆管机械振动提高临界热通量的实验研究

获取原文
获取原文并翻译 | 示例
   

获取外文期刊封面封底 >>

       

摘要

In order to gain an understanding of the relationship between critical heat flux (CHF) and flow-induced vibration (FIV), an experimental investigation was carried out with vertical round tube at the atmosphere. In the both condition of departure from nucleate boiling (DNB) and the liquid film dryout (LFD), CHF increases up to 12.6% with vibration intensity, represented by vibrational Reynolds number (Re_v). CHF enhancement by tube vibration seems to come from the reinforced flow turbulent mixing and the increment of deposition of droplet into the liquid film. Based on the experimental results, an empirical correlation is proposed for the prediction of CHF enhancement ratio. The correlation predicts the CHF enhancement ratio (E_n) with reasonable accuracy, with an average error rate of 4.5 and 26.5% for RMS. Vibration is an effective method for heat transfer enhancement as well as CHF. Nonetheless, the risk of system failure by FIV has made it very difficult to take advantage of vibration in heat transfer facilities. Therefore, it is necessary to find out optimal fuel design enhancing the CHF but preventing FIV damage in an acceptable vibration range.
机译:为了了解临界热通量(CHF)和流致振动(FIV)之间的关系,在大气中使用垂直圆管进行了实验研究。在偏离核沸腾(DNB)和液膜变干(LFD)的两种情况下,CHF随振动强度(以雷诺数(Re_v)表示)增加至12.6%。管振动引起的CHF增强似乎来自增强的湍流混合和液滴在液膜中的沉积增加。基于实验结果,提出了经验相关性用于预测CHF增强率。相关性以合理的精度预测CHF增强率(E_n),RMS的平均错误率分别为4.5和26.5%。振动是增强传热以及CHF的有效方法。然而,FIV导致系统故障的风险使利用传热设备中的振动变得非常困难。因此,有必要找出最佳的燃料设计,以提高CHF,但要在可接受的振动范围内防止FIV损坏。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2004年第1期|p.47-58|共12页
  • 作者单位

    Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong, Yuseong-gu, Daejeon 305-701, South Korea;

  • 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 原子能技术;
  • 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