| 转运通道中燃料组件沸腾传热的试验研究 |
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| 引用本文： | 毛喜道,夏虹.转运通道中燃料组件沸腾传热的试验研究[J].原子能科学技术,2020,54(4):624-628. |
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| 作者姓名： | 毛喜道 夏虹 |
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| 作者单位： | 哈尔滨工程大学 核科学与技术学院，黑龙江 哈尔滨150001；中国核电工程有限公司，北京100840 |
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| 摘 要： | 在压水堆换料过程中，乏燃料组件要通过水下通道完成从反应堆厂房到乏燃料水池的运输。为获得乏燃料组件在换热条件较恶劣的承载器顶角区域的传热特性，开展了试验研究，测量得到了2 400～20 000 W/m2不同热流密度下承载器顶角区域3根燃料棒顶部的沸腾换热系数，并拟合得到沸腾传热关联式。研究结果可为今后工程应用中评估燃料组件在转运过程中的热工安全状态和表面最高温度提供参考。
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| 关 键 词： | 燃料转运通道 燃料组件 池沸腾传热 |
Experimental Study on Boiling Heat Transfer of Fuel Assembly in Fuel Transfer Tube |
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| MAO Xidao,XIA Hong.Experimental Study on Boiling Heat Transfer of Fuel Assembly in Fuel Transfer Tube[J].Atomic Energy Science and Technology,2020,54(4):624-628. |
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| Authors: | MAO Xidao XIA Hong |
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| Affiliation: | College of Nuclear Science and Technology, Harbin Engineering University, Harbin 150001, China;China Nuclear Power Engineering Co., Ltd., Beijing 100840, China |
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| Abstract: | During the PWR refueling process, the spent fuel assembly is transferred from the reactor building to the spent fuel pool through an underwater tube. In order to obtain the heat transfer characteristics of the spent fuel assembly in the top-corner area of the carrier with poor heat transfer conditions, the experimental study was carried out. The pool boiling heat transfer coefficients of the three fuel rods in the top-corner area of the carrier under different heat flux densities (2 400-20 000 W/m2) were mea-sured and obtained. The boiling heat transfer correlations were obtained by fitting the experimental data. The results can provide a reference for evaluating the thermal safety state and the maximum surface temperature of the fuel assembly during the transportation process in future engineering applications. |
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| Keywords: | fuel transfer tube fuel assembly pool boiling heat transfer |
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