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作 者:崔大伟 陈硕[2] 顾汉洋[2] 林继铭 Cui Dawei;Chen Shuo;Gu Hanyang;Lin Jiming(China Nuclear Power Technology Research Institute,Shenzhen,Guangdong,518026,China;Shanghai Jiaotong University,Shanghai,200240,China)
机构地区:[1]中广核研究院有限公司,广东深圳518026 [2]上海交通大学,上海200240
出 处:《核动力工程》2021年第4期33-38,共6页Nuclear Power Engineering
摘 要:在超临界水多功能实验装置上开展了三角布置棒束内超临界水流动传热实验研究,通过实验观测到了通道内棒束周向温度分布不均匀现象和定位格架导致的传热强化现象,获得不同热流密度、质量流量及压力范围内的传热实验数据,拟合得到预测偏差为±15%的三角布置棒束超临界水传热关系式。The experimental research of heat transfer to supercritical water in a triangular-lattice configuration has been performed on the supercritical water multipurpose test loop.Circumferential non-uniformed wall temperature distribution and heat transfer enhancement induced by the grids were observed in the bundles.The heat transfer data under conditions of different heat flux,mass flux and pressure were obtained.Finally,an empirical correlation with the prediction deviation of±15%was developed to predict the supercritical heat transfer behaviors in the triangular-lattice.
分 类 号:TL33[核科学技术—核技术及应用]
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