Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket
Lian, Qiang, Tang, Simiao, Zhu, Longxiang, Zhang, Luteng, Sun, Wan, Bu, Shanshan, Pan, Liangming, Tian, Wenxi, Qiu, Suizheng, Su, G.H., Wu, Xinghua, Wang, Xiaoyu
Published in Nuclear engineering and technology (01.11.2023)
Published in Nuclear engineering and technology (01.11.2023)
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Journal Article
Flow blockage analysis for fuel assembly in a lead-based fast reactor
Wang, Chenglong, Wu, Di, Gui, Minyang, Cai, Rong, Zhu, Dahuan, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
Published in Nuclear engineering and technology (01.10.2021)
Published in Nuclear engineering and technology (01.10.2021)
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Journal Article
Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor
Wang, Chenglong, Liu, Limin, Liu, Minghao, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
Published in Annals of nuclear energy (01.11.2017)
Published in Annals of nuclear energy (01.11.2017)
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Journal Article
Study on iterative algorithm of full plate cross-flow and counter-flow printed circuit heat exchanger for fluoride-salt-cooled high-temperature advanced reactor
Li, Xinze, Zhang, Dalin, Li, Xinyu, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
Published in International Journal of Advanced Nuclear Reactor Design and Technology (01.06.2023)
Published in International Journal of Advanced Nuclear Reactor Design and Technology (01.06.2023)
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Journal Article
CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR
Wang, Yingjie, Wang, Mingjun, Ju, Haoran, Zhao, Minfu, Zhang, Dalin, Tian, Wenxi, Liu, Tiancai, Qiu, Suizheng, Su, G.H.
Published in Nuclear engineering and technology (01.07.2020)
Published in Nuclear engineering and technology (01.07.2020)
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Journal Article
Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR
Wang, Mingjun, Wang, Lianfa, Jing, Jianping, Gao, Xinli, Qiu, Suizheng, Tian, Wenxi, Su, G.H.
Published in Nuclear engineering and design (01.12.2017)
Published in Nuclear engineering and design (01.12.2017)
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Journal Article
Preliminary design and assessment of a heat pipe residual heat removal system for the reactor driven subcritical facility
Zhang, Wenwen, Sun, Kaichao, Wang, Chenglong, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
Published in Nuclear engineering and technology (01.12.2021)
Published in Nuclear engineering and technology (01.12.2021)
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Journal Article
Uncertainty analysis of Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) using coupled DAKOTA with RELAP-3D method
Wang, Chenglong, Sun, Kaichao, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
Published in Nuclear engineering and design (01.12.2017)
Published in Nuclear engineering and design (01.12.2017)
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Journal Article
Large eddy simulation on the turbulent mixing phenomena in 3×3 bare tight lattice rod bundle using spectral element method
Ju, Haoran, Wang, Mingjun, Wang, Yingjie, Zhao, Minfu, Tian, Wenxi, Liu, Tiancai, Su, G.H., Qiu, Suizheng
Published in Nuclear engineering and technology (01.09.2020)
Published in Nuclear engineering and technology (01.09.2020)
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Journal Article
Numerical investigation of the fluid-solid mixture flow using the FOCUS code
Guo, Kailun, Chen, Ronghua, Li, Yonglin, Qiu, Suizheng, Su, G.H.
Published in Progress in nuclear energy (New series) (01.05.2017)
Published in Progress in nuclear energy (New series) (01.05.2017)
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Journal Article
Analysis of KROTOS KS-2 and KS-4 steam explosion experiments with TEXAS-VI
Chen, Ronghua, Wang, Jun, Su, G.H., Qiu, Suizheng, Corradini, M.L.
Published in Nuclear engineering and design (01.12.2016)
Published in Nuclear engineering and design (01.12.2016)
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Journal Article
CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment
Ye, Linrong, Yu, Hao, Wang, Mingjun, Wang, Qianglong, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
Published in Nuclear engineering and technology (01.01.2022)
Published in Nuclear engineering and technology (01.01.2022)
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Journal Article
Impact of axial power distribution on thermal-hydraulic characteristics for thermionic reactor
Dai, Zhiwen, Wang, Chenglong, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
Published in Nuclear engineering and technology (01.12.2021)
Published in Nuclear engineering and technology (01.12.2021)
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Journal Article
Development of a three-dimensional method for thermal-hydraulics/neutronics coupling analysis and its application on CFETR helium-cooled solid breeder blanket
Lian, Qiang, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
Published in International Journal of Advanced Nuclear Reactor Design and Technology (2021)
Published in International Journal of Advanced Nuclear Reactor Design and Technology (2021)
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Journal Article
Experimental investigation of entrainment effect on the countercurrent flow in the Hot Leg and Pressurizer Surge Line assembly of third-generation passive nuclear reactors
Yu, Jiangtao, Zhang, Dalin, Shi, Leitai, Tian, Wenxi, Su, G.H., Qiu, S.Z.
Published in Nuclear engineering and design (15.08.2018)
Published in Nuclear engineering and design (15.08.2018)
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Journal Article
Thermal hydraulic design and analysis of Thorium-based Advanced CANDU Reactor (TACR)
Wei, Shiying, Wang, Chenglong, Tian, Wenxi, Qiu, Suizheng, Su, G.H.
Published in Nuclear engineering and design (01.11.2017)
Published in Nuclear engineering and design (01.11.2017)
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