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U型管高压汽-液两相流动密度波型不稳定性的实验研究 被引量:3

Experimental Study on Density-Wave Instability of High Pressure Steam-Water Two-Phase Flow in U-Type Tube
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摘要 在系统压力P=4~10MPa,质量流速G=450~1200kg/m^2·s,人口过冷度△T_(sub)=10~70℃,热负荷q=O~650kW/m^2的工况范围内,采用φ20×2mm的23Crl8Ni不锈钢U型管,在高压试验台上进行了密度波型脉动的研究;分析了系统压力、质量流速、入口过冷度、热负荷对它的影响。结果表明,随着压力的增加,系统稳定性增加;随着质量流速增加,界限热负荷增加,界限干度下降;进口过冷度对密度波型脉动呈现单值性影响,随着进口过冷度下降,界限热负荷降低。根据实验结果及量纲分析,得出了预测界限热负荷的无因次关联式,与试验值相比,误差在15%以内。 Experiments on the density wave instability of the high pressure steam water two-phase flow in a U-type tube have been performed within the range of pressure from 4 to 10MPa, mass flux from 450 to 1200 kg/m^2·s, inlet subcooling from 10 to 70℃ and heat flux from 0 to 650 kW/m^2. The outer diameter of the U-type tube is 20mm, and the wall thickness is 2mm. The effects of pressure, mass flux, inlet subcooling, and heat flux on the density wave instability were studied and discussed. The experimental results showed that the boiling flow system was more stable as the pressure increased. Heat flux threshold increased with an increase in mass velocity, but steam quality threshold decreased. When inlet subcooling reduced, heat flux threshold decreased. Based on the experimental results and dimensionless analysis, an empirical correlation to predict heat flux threshold was presented. The errors between the predicted threshold and the experimental data lied in a range of 15%.
出处 《核动力工程》 EI CAS CSCD 北大核心 2005年第6期564-567,共4页 Nuclear Power Engineering
关键词 U型管 高压 汽-液两相流 密度波型脉动 U-type tube, High pressure, Steam- water two phase flow, Density wave instability
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