| 两相条件下主泵特性试验研究 |
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| 引用本文： | 苏前华,王阔,邢军,洪荣坤,彭帆,卢冬华.两相条件下主泵特性试验研究[J].核动力工程,2021,42(1):129-132. |
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| 作者姓名： | 苏前华 王阔 邢军 洪荣坤 彭帆 卢冬华 |
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| 作者单位： | ;1.中广核研究院有限公司综合热工水力与安全实验室 |
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| 摘 要： | 针对自主研发百万千瓦级核电主泵项目，本研究在专设台架上对经过模化缩比后的模型试验泵开展特性研究，首先开展泵单相液体条件下正常工况、水轮机工况、耗能工况、卡轴工况、飞逸工况的流动特性试验，之后逐一针对两相空泡份额为0.1、0.2、0.3、0.4、0.5、0.6、0.7、0.8、0.9、1.0条件下的泵在上述具体运行工况开展研究，最终利用比例定律，对多个转速下的实验数据进行整理，进而掌握了其扬程在不同空泡、不同流量下的变化规律，在单相液体基础上的泵扬程比例定律曲线随着空泡份额的增大会存在不断“漂移”和再回归的过程，当空泡份额达到0.7左右时，“漂移”程度最大，当流体变为单相气体时，实现再回归，上述实验结果为后续核主泵设计的深入研究及一回路安全分析提供了数据支撑。
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| 关 键 词： | 核电主泵 两相流 空泡份额 比例定律 扬程 |
Experimental Research on Pump Characteristics under Two-Phase Condition |
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| Su Qianhua,Wang Kuo,Xing Jun,Hong Rongkun,Peng Fan,Lu Donghua.Experimental Research on Pump Characteristics under Two-Phase Condition[J].Nuclear Power Engineering,2021,42(1):129-132. |
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| Authors: | Su Qianhua Wang Kuo Xing Jun Hong Rongkun Peng Fan Lu Donghua |
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| Affiliation: | (Comprehensive Thermal-Hydraulic and Safety Laboratory of China Nuclear Power Research Institute Co.,Ltd.,Shenzhen,Guangdong,518000,China) |
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| Abstract: | For indigenous mega-kilowatt class reactor cooling pumps(RCPs) project, the performance characteristics of subject pump based on the scale model of RCPs are fully researched in the specialized experiment system. The pump characteristics under single-phase liquid condition in normal speed case, turbine case, energy dissipation case, rotor locked case and runaway speed case are firstly obtained. Furthermore, the pump two-phase specific operating conditions under the void fraction of 0.1, 0.2, 0.3, 0.4, 0.5, 0.6, 0.7, 0.8, 0.9 and 1.0 are studied one by one. Finally, we use the proportion law to sort out the experimental data under multiple pump speeds, and then obtain the change rule of the pump head under different void fractions and different flows. The curve of pump head proportional law on the basis of single-phase liquid has a process of continuous drift and regression with the increase of the void fraction. When the void fraction reaches about 0.7, the drift degree is the largest, and when the fluid changes to single-phase gas, the regression is realized. The above experimental results provide data support for further research of nuclear main pump design and primary circuit safety analysis. |
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| Keywords: | Nuclear pump Two phase flow Void fraction Proportion law Pump head |
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