...
首页> 外文期刊>Proceedings of the Institution of Mechanical Engineers, Part C. Journal of mechanical engineering science >Nucleate boiling heat transfer coefficients of halogenated refrigerants up to critical heat fluxes
【24h】

Nucleate boiling heat transfer coefficients of halogenated refrigerants up to critical heat fluxes

机译:直至临界热通量的卤化制冷剂的核沸腾传热系数

获取原文
获取原文并翻译 | 示例
           

摘要

In this work, nucleate pool boiling heat transfer coefficients (HTCs) of five refrigerants of differing vapour pressures are measured on a horizontal, smooth copper surface of 9.53 × 9.53 mm. The tested refrigerants are R123, R152a, R134a, R22, and R32 and HTCs are taken from 10kW/m{sup}2 to the critical heat flux (CHF) of each refrigerant. Wall and fluid temperatures are measured directly by thermocouples located underneath the test surface and in the liquid pool, respectively. Test results show that nucleate pool boiling HTCs of halogenated refrigerants increase as the heat flux and vapour pressure increase. This typical trend is maintained even at high heat fluxes above 200 kW/m{sup}2. Zuber's prediction equation for CHF is quite accurate showing a maximum deviation of 21 per cent for all refrigerants tested. For all refrigerants, Stephan and Abdelsalam's well-known correlation underpredicted nucleate boiling HTC data up to the CHF with an average deviation of 21.3 per cent, while Cooper's correlation overpredicted the data with an average deviation of 14.2 per cent. On the other hand, Gorenflo's and Jung et al.'s correlations showed 5.8 and 6.4 per cent deviations, respectively, in the entire nucleate boiling range up to the CHF.
机译:在这项工作中,在9.53×9.53 mm的水平,光滑铜表面上,测量了五种不同蒸气压的制冷剂的核池沸腾传热系数(HTC)。测试的制冷剂为R123,R152a,R134a,R22和R32,HTC的取值范围为10kW / m {sup} 2至每种制冷剂的临界热通量(CHF)。分别通过位于测试表面下方和液体池中的热电偶直接测量壁和流体温度。测试结果表明,随着热通量和蒸气压的增加,卤化制冷剂的成核池沸腾HTC也会增加。即使在高于200 kW / m {sup} 2的高热通量下,也能保持这种典型趋势。 Zuber的CHF预测公式非常准确,显示所有测试制冷剂的最大偏差为21%。对于所有制冷剂,Stephan和Abdelsalam的众所周知的相关性均低估了直到CHF的成核沸腾HTC数据,平均偏差为21.3%,而Cooper的相关性则高估了数据,平均偏差为14.2%。另一方面,Gorenflo和Jung等人的相关性显示,在直至CHF的整个核沸腾范围内,偏差分别为5.8%和6.4%。

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