首页> 外文期刊>Nuclear Engineering and Design >Critical heat flux under zero flow conditions in vertical annulus with uniformly and non-uniformly heated sections
【24h】

Critical heat flux under zero flow conditions in vertical annulus with uniformly and non-uniformly heated sections

机译:垂直环空中零流量条件下具有均匀和不均匀加热截面的临界热通量

获取原文
获取原文并翻译 | 示例
           

摘要

The experimental study of water CHF (critical heat flux) under zero flow conditions has been carried out in an annulus flow channel with uniformly and non-uniformly heated sections over a pressure range of 0.52-14.96 MPa. In the present boiling system, the CHFs occur in the upper region of the heated section, in contrast to the results in the experiments for boiling tubes conducted by several investigators. The general trend of the CHF with pressure is that the CHF increases up to a mediuin pressure of about 6-8 MPa and decreases as the pressure is further increased. A comparison of the present data with the existing flooding CHF correlations shows that the correlations depend greatly on the effect of the heat flux distribution. When the correction terms with the density ratio and the effect of the heat flux distribution proposed in the present work are used with the CHF correlation based on the Wallis flooding correlation, it predicts the measured flooding CHF within an RMS error of 9.0/100.
机译:在零流量条件下的水CHF(临界热通量)的实验研究已在具有均匀加热区域和不均匀加热区域且压力范围为0.52-14.96 MPa的环形流动通道中进行。在当前的沸腾系统中,CHF出现在加热部分的上部区域,这与几个研究人员进行的沸腾管实验结果相反。 CHF随压力变化的总体趋势是,CHF升高到约6-8 MPa的中等压力,并随着压力的进一步升高而降低。将当前数据与现有的洪水CHF相关性进行比较表明,这些相关性很大程度上取决于热通量分布的影响。当基于沃利斯泛滥相关性将带有密度比的校正项和热通量分布的影响与CHF相关性一起使用时,它会在RMS / 100的RMS误差范围内预测测得的泛滥CHF。

著录项

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