Search Results - "Cong, TengLong"

Development of a refined helical fuel mixing model and application to a helical fuel rod bundle by Fu, JunSen, Xiao, Yao, Li, JunLong, Zhang, Qi, Cong, TengLong, Gu, HanYang

“…Fuel assemblies have a decisive impact on the performance and safety of nuclear reactors. Helical fuel has huge potential for application in small module…”
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Numerical study on the heat transfer characteristics of a liquid lead–bismuth eutectic in a D-type channel by Liu, Hong, Zhang, Zhigang, Du, Haisu, Cong, Tenglong

“…A printed circuit heat exchanger (PCHE) can offer superior performance in area concentration and heat transfer efficiency. A PCHE with a liquid lead–bismuth…”
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Numerical Study of Bubble Coalescence and Breakup in the Reactor Fuel Channel with a Vaned Grid by Cong, Tenglong, Zhang, Xiang

“…The characteristics of bubbles of different sizes in fuel assembly are vital to two-phase flow resistance and heat transfer capacity. However, due to the swirl…”
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Development and Application of 3D Steam Generator Thermohydraulics Analysis Code SGTH-Porous3D by CONG Tenglong;CONG Zheng;LIU Maolong;XIAO Yao;GUO Hui;GU Hanyang

“…As the pressure and heat transfer boundaries between primary and secondary sides, the steam generator (SG) should be integrated during operation. However, SG…”
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Study on secondary side flow of steam generator with coupled heat transfer from primary to secondary side by Cong, Tenglong, Tian, Wenxi, Qiu, Suizheng, Su, Guanghui

“…Thermohydraulics characteristics in the secondary side of AP1000 steam generator (SG) are simulated based on the porous media models. The drift flux two-phase…”
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Development and evaluation of fuel performance analysis code FuSPAC by Cong, Tenglong, Chen, Hao, Chen, Chao, Zhang, Shaohong, Gu, Hanyang

“…The nuclear fuel rod should maintain self-sustainable nuclear fission, as the first safety barrier to prevent the leakage of radioactive products. The fuel rod…”
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Multiphysics analysis of a metal hydride moderated megawatt heat pipe reactor with burnable poisons by Feng, KuaiYuan, Hu, Jipu, Wang, Yihu, Cong, Tenglong, Gu, Hanyang, Guo, Hui

“…With the development of nuclear energy, microreactors have received increasing interest among researchers in recent years. In this paper, a megawatt heat pipe…”
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Uncertainty Analysis on k-ε Turbulence Model in the Prediction of Subcooled Boiling in Vertical Pipes by Zhang, Xiang, Xia, Genglei, Cong, Tenglong, Peng, Minjun, Wang, Zhenhong

“…Computational fluid dynamics (CFD) has become an effective method for researching two-phase flow in reactor systems. However, the uncertainty analysis of…”
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Uncertainties Analysis on the Prediction of Flow and Heat Transfer of Liquid Sodium with CFD Technology by Cui, Yuning, Zheng, Lingyun, Zhang, Rui, Cong, Tenglong, Li, Xinyu, Liu, Zhanwei, Deng, Hang

“…The prediction of flow and heat transfer characteristics of liquid sodium with CFD technology is of significant importance for the design and safety analysis…”
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Three-dimensional study on steady thermohydraulics characteristics in secondary side of steam generator by Cong, Tenglong, Tian, Wenxi, Su, Guanghui, Qiu, Suizheng, Xie, Yongcheng, Yao, Yangui

“…Steam generator (SG), as the primary-to-secondary heat exchanger and pressure boundary of primary loop, should be integrated and perform well in heat transfer…”
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Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithm by Cong, Tenglong, Chen, Ronghua, Su, Guanghui, Qiu, Suizheng, Tian, Wenxi

“…► ANN was trained to predict the CHF with a better accuracy than GA. ► CHF increases with jet velocity. ► CHF decreases with an increase in L/ d and the number…”
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Numerical Study on Laminar-Turbulent Transition Flow in Rectangular Channels of a Nuclear Reactor by Wang, Zhenying, Zhang, Rui, Yu, Ting, Liu, Zhiyun, Huang, Yu, Wang, Jianjun, Cong, Tenglong

“…Laminar-turbulent transition flow can be observed in thermal engineering applications, but the flow resistance and heat transfer characteristics are not fully…”
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Investigation on the Subcooled Boiling in Vertical Pipe With Uncertainties From Boundary Conditions by Using FLUENT by Zhang, Xiang, Zhang, Rui, Lv, Xindi, Cong, Tenglong

“…Subcooled boiling flow taking place in the reactor system plays a critical role in the safety of nuclear power plants. It has been studied by experiments and…”
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Strategy Evaluation for Cavity Flooding during an ESBO Initiated Severe Accident by Cong, Tenglong, Wei, Wei, Peng, Minjun, Jiang, Nan

“…Intentional depressurization and cavity flooding are two important measures in current severe accident management guidelines (SAMGs). An extreme scenario of an…”
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铅铋冷却绕丝燃料组件横流特性分析 by 丛腾龙, 王俊杰, 肖瑶, 刘茂龙, 顾汉洋

“…TL33;…”
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燃料组件偏置及弯曲对沸腾临界影响研究 by 龚佳奇, 丛腾龙, 肖瑶, 顾汉洋, 丁铭

“…TL334; 反应堆燃料组件可能因为制造、安装的偏差或外力等因素,导致燃料棒发生整体偏置或弯曲的现象,对传热以及沸腾临界造成不利影响.为评估影响大小,本文建立基于欧拉两流体模型和改进…”
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螺旋十字燃料组件热流力耦合特性数值模拟研究 by 刘峪洁, 丛腾龙, 肖瑶, 郭辉, 顾汉洋

“…TL352; 作为一种新型反应堆燃料组件,螺旋十字燃料(HCF)组件具有导热距离短、交混强度高、无需定位格架等优势,可在保证反应堆安全裕度的同时提高堆芯功率,但其依靠相邻棒束接触形成的自支撑结构进行定位易使接触位置发生应力集中,危害包壳的完整性.针对这一问题,本文开展了典型…”
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螺旋十字燃料棒束热力耦合特性研究 by 丛腾龙, 刘峪洁, 郭辉, 肖瑶, 顾汉洋

“…TL352; 螺旋十字燃料(Helical-Cruciform…”
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双孔对直接接触冷凝特性影响的实验研究 by 叶亚楠, 肖瑶, 丛腾龙, 张伟, 顾汉洋

“…TL331; 本文对双孔直接接触冷凝进行了实验研究.实验的蒸汽质量流速范围为50～500…”
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LBE下降流场中传热管微裂纹处蒸汽泡动力学数值模拟研究 by 董伟健, 丛腾龙, 朱俊志, 肖瑶, 邹旭毛, 顾汉洋

“…TL99; 铅铋冷却快堆(Lead-Bismuth Cooled Fast Reactor)蒸汽发生器传热管发生破口(Steam Generator…”
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