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NUCLEAR TECHNIQUES, Volume. 47, Issue 9, 090605(2024)

Numerical study of coupled heat transfer between primary and secondary sides of helical coiled tube steam generator for liquid metal fast reactor

Jialun LIU1、*, Liang NING1, Jinpeng LIN1, Jie XIN1, Min LI2, and Huixiong LI3
Author Affiliations
  • 1College of New Energy, Xi'an Shiyou University, Xi'an 710065, China
  • 2Ningxia Special Equipment Inspection and Testing Institute, Yinchuan 750000, China
  • 3State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an JiaoTong University, Xi'an 710049, China
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    [1] JIANG Xing, ZHANG Ming, XIE Yongcheng et al. Three-dimensional numerical simulation of secondary side flow field of steam generator[J]. Atomic Energy Science and Technology, 42, 438-443(2008).

    [2] WANG Hongyang, RUAN Shenhui, WEN Qinglong et al. Numerical study of fast reactor steam generator based on porous media model[J]. Nuclear Power Engineering, 40, 51-55(2019).

    [3] Dehbi A, Badreddine H. CFD prediction of mixing in a steam generator mock-up: comparison between full geometry and porous medium approaches[J]. Annals of Nuclear Energy, 58, 178-187(2013).

    [4] Wang C L, Cong T L, Qiu S Z et al. Numerical prediction of subcooled wall boiling in the secondary side of SG tubes coupled with primary coolant[J]. Annals of Nuclear Energy, 63, 633-645(2014).

    [5] Cong T L, Tian W X, Su G H et al. Three-dimensional study on steady thermohydraulics characteristics in secondary side of steam generator[J]. Progress in Nuclear Energy, 70, 188-198(2014).

    [6] LIU Le, HUANG Yu, XU Liangwang. Numerical study on heat transfer characteristic of two-phase flow in SG secondary side[J]. Nuclear Science and Engineering, 36, 611-616(2016).

    [7] ZHAO Yu, SUN Baozhi, BAO Jie et al. Numerical simulation of two-phase flow friction pressure drop and heat transfer for nucleate boiling in helically coiled tube[J]. Atomic Energy Science and Technology, 52, 590-599(2018).

    [8] Wang M L, Zheng M G, Chao M K et al. Experimental and CFD estimation of single-phase heat transfer in helically coiled tubes[J]. Progress in Nuclear Energy, 112, 185-190(2019).

    [9] LIU Fayu, ZHANG Xiaoying, CHEN Jiayue et al. Analysis of coupled flow and heat transfer in primary and secondary sides of helical coil once-through tube steam generator[J]. Nuclear Power Engineering, 41, 24-29(2020).

    [10] CHEN Qi, LING Yufan, ZHAO Pengcheng et al. Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor[J]. Nuclear Techniques, 46, 110602(2023).

    [11] WANG Cong, ZHANG Wei, LI Jingsong et al. A method study of numerical simulation on flow field of spiral tube in steam generator shell side[J]. Nuclear Power Engineering, 42, 171-175(2021).

    [12] ZHAO Houjian, XIE Xiaoyang, GAO Weikai et al. Numerical simulation of liquid lead-bismuth eutectic cross flow heat transfer over tube bundles[J]. Journal of Engineering Thermophysics, 42, 1837-1843(2021).

    [13] YANG Yupeng, WANG Chenglong, ZHANG Dalin et al. Numerical study of liquid metal helical coil once-through tube steam generator[J]. Atomic Energy Science and Technology, 55, 1288-1295(2021).

    [14] DING Xueyou, CHEN Zhiqiang, WEN Qinglong et al. Numerical investigation on thermal hydraulics of helical coil tube once through steam generator for LBE fast reactor[J]. Nuclear Power Engineering, 42, 21-26(2021).

    [15] Niu X J, Luo S S, Fan L L et al. Numerical simulation on the flow and heat transfer characteristics in the one-side heating helically coiled tubes[J]. Applied Thermal Engineering, 106, 579-587(2016).

    [16] Qiu G D, Cai W H, Wu Z Y et al. Numerical simulation of forced convective condensation of propane in a spiral tube[J]. Journal of Heat Transfer, 137, 041502(2015).

    [17] Magnini M, Pulvirenti B, Thome J R. Numerical investigation of hydrodynamics and heat transfer of elongated bubbles during flow boiling in a microchannel[J]. International Journal of Heat and Mass Transfer, 59, 451-471(2013).

    [19] Rickard C L, Dwyer O E, Dropkin D. Heat transfer rates to cross-flowing mercury in a staggered tube bank[J]. Transactions of the American Society of Mechanical Engineers, 80, 642-652(1958).

    [20] Santini L, Cioncolini A, Butel M et al. Flow boiling heat transfer in a helically coiled steam generator for nuclear power applications[J]. International Journal of Heat and Mass Transfer, 92, 91-99(2016).

    [21] Cinotti L, Bruzzone M, Meda N et al. Steam generator of the international reactor innovative and secure[C], 983-990(2009).

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    Jialun LIU, Liang NING, Jinpeng LIN, Jie XIN, Min LI, Huixiong LI. Numerical study of coupled heat transfer between primary and secondary sides of helical coiled tube steam generator for liquid metal fast reactor[J]. NUCLEAR TECHNIQUES, 2024, 47(9): 090605

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Jan. 18, 2024

    Accepted: --

    Published Online: Nov. 13, 2024

    The Author Email: LIU Jialun (ljl.619@163.com)

    DOI:10.11889/j.0253-3219.2024.hjs.47.090605

    Topics

    laser devices and laser physics
    Lasers and Laser Optics
    Laser physics
    laser manufacturing
    Instrumentation, Measurement and Metrology