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作 者:刘可心 闫震 徐建军[2] 丁雷[2] 丁铭 曹夏昕[1] LIU Kexin;YAN Zhen;XU Jianjun;DING Lei;DING Ming;CAO Xiaxin(Heilongjiang Provincial Key Laboratory of Nuclear Power System&Equipment,Harbin Engineering University,Harbin 150001,China;Nuclear Power Institute of China,Chengdu 610041,China)
机构地区:[1]哈尔滨工程大学黑龙江省核动力装置性能与设备重点实验室,黑龙江哈尔滨150001 [2]中国核动力研究设计院,四川成都610041
出 处:《哈尔滨工程大学学报》2025年第2期374-382,共9页Journal of Harbin Engineering University
基 金:国家自然基金联合基金重点项目(U2167207);中央高校基本科研业务费——博士研究生科研创新基金项目(3072023GIP1502)。
摘 要:为了探究高过冷沸腾条件下板状燃料元件冷却剂通道内的流动换热问题,针对窄矩形通道内的高过冷沸腾现象开展了实验研究。在0.2 MPa压力下的窄矩形通道内,对过冷度为25~50℃且质量流速为400~700 kg/(m^(2)·s)的去离子水单面加热至沸腾,壁面热流密度为70~375 kW/m^(2),出口空泡份额为0.0029~0.0838。采用压差传感器和K型铠装热电偶分别获取实验段内压降数据和壁面温度数据。基于实验数据对文献中关于两相流动和沸腾换热的经验关系式进行评价,结果显示:已有的沸腾换热系数和两相摩擦压降模型对高过冷沸腾的预测能力较差。建立了适用于窄矩形通道内高过冷沸腾情况下的沸腾换热系数和两相摩擦压降预测模型,本文模型对沸腾换热系数和两相摩擦压降预测的平均绝对误差分别为12.45%和16.72%,精度优于已有模型。通过与文献中的实验数据对比进一步验证了本文模型的可靠性。Experimental research was conducted on the flow and heat transfer in the coolant channel of plate fuel elements under high sub-cooled boiling conditions.Inside a narrow rectangular channel at a pressure of 0.2 MPa,deionized water with a sub-cooling range of 25~50℃and a mass flow rate of 400~700 kg/(m^(2)·s)was heated by one side to induce boiling.The wall heat flux ranged from 70 kW/m^(2) to 375 kW/m^(2),and the outlet void fraction varied from 0.0029 to 0.0838.In the experiment,pressure difference sensors and K-type armored thermocouples were used to obtain pressure drop data and wall temperature data within the experimental section.The experimental data were used to evaluate the correlations between two-phase flow and boiling heat transfer in the references.The results show that the existing boiling heat transfer coefficient and two-phase friction pressure drop models have poor predictive ability for high sub-cooled boiling.The prediction model of boiling heat transfer coefficient and two-phase friction pressure drop suitable for high sub-cooled boiling in narrow rectangular channels was established.The mean absolute errors of the this model for predicting boiling heat transfer coefficient and two-phase friction pressure drop were 12.45%and 16.72%,respectively.These results are better than those of the existing models.The reliability of the this model was further verified by comparing it with experimental data in the literature.
关 键 词:窄矩形通道 高过冷沸腾 两相换热系数 两相摩擦压降 传热模型 分相流模型 均相流模型 实验研究
分 类 号:TL334[核科学技术—核技术及应用]
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