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作 者:张立强[1] 公茂琼[2] 吴剑峰[2] 徐烈[1]
机构地区:[1]上海交通大学低温与制冷研究所,上海200030 [2]中国科学院理化技术研究所,北京100080
出 处:《低温与超导》2006年第2期97-99,104,共4页Cryogenics and Superconductivity
基 金:国家自然科学基金资助项目(50576102)
摘 要:实验测量了二元混合工质HFC23/CFCl3池核沸腾传热特性。加热面为紫铜表面,实验测量的压力范围为0.1-0.55MPa。热流范围为10kW/m^3-300kW/m^2。实验数据同现有经验关联式的计算结果相比较,发现Fujita and Tsutsu/关联式和Thome and Shakir关联式对混合工质HFC23/CFC13的传热系数预测较准确,预测值与实验值之差≤±20%。The heat transfer data of nucleate pool boiling on a smooth flat surface were measured for binary mixtures of HFC23/ CFC13. The experiment was carried out at different pressures from 0.1 to 0. 5 5MPa, while the heat fluxes in the experiment vary between 300 and 10 kW/m^2. Predicted results with three well -known correlations were compared with the experimental data. Correlations by Fujita and Tsutsui and Thome and Shakir show acceptable accuracy in prediction. Most of the data deviations were within ±20% with the correlations.
分 类 号:TB64[一般工业技术—制冷工程] TQ021.3[化学工程]
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