• NUCLEAR TECHNIQUES
  • Vol. 45, Issue 12, 120605 (2022)
Weijian DONG1, Tenglong CONG1、*, Junzhi ZHU2, Yao XIAO1, Xumao ZOU2, and Hanyang GU1
Author Affiliations
  • 1School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200030, China
  • 2China Nuclear Power Technology Research Institute, Shenzhen 518000, China
  • show less
    DOI: 10.11889/j.0253-3219.2022.hjs.45.120605 Cite this Article
    Weijian DONG, Tenglong CONG, Junzhi ZHU, Yao XIAO, Xumao ZOU, Hanyang GU. Numerical simulation of steam bubble dynamics at microcrack in LBE descending flow field[J]. NUCLEAR TECHNIQUES, 2022, 45(12): 120605 Copy Citation Text show less
    References

    [1] WEI Shiying, WANG Chenglong, TIAN Wenxi et al. Research progress in key thermal-hydraulic issue of lead-based fast reactor[J]. Atomic Energy Science and Technology, 53, 326-336(2019).

    [2] Li X Y, Cheng J, Zhang D L et al. Design and optimization of passive residual heat removal system for lead-bismuth reactor SVBR-100[J]. International Journal of Energy Research, 45, 1-12146(2021).

    [3] Cinotti L, Smith C F, Sekimoto H et al. Lead-cooled system design and challenges in the frame of Generation IV International Forum[J]. Journal of Nuclear Materials, 415, 245-253(2011).

    [4] Zhang Y, Wang C L, Lan Z K et al. Review of thermal-hydraulic issues and studies of lead-based fast reactors[J]. Renewable and Sustainable Energy Reviews, 120, 109625(2020).

    [5] HAN Jinsheng, LIU Bin, LI Wenqiang. Summary of lead-cooled fast reactor research[J]. Nuclear Science and Technology, 87-97(2018).

    [6] Wang G. A review of research progress in heat exchanger tube rupture accident of heavy liquid metal cooled reactors[J]. Annals of Nuclear Energy, 109, 1-8(2017).

    [7] Zhao X H, Liao Y X, Wang M J et al. Numerical simulation of micro-crack leakage on steam generator heat transfer tube[J]. Nuclear Engineering and Design, 382, 111385(2021).

    [8] Zhang Y, Wang C L, Cai R et al. Experimental investigation on flow and heat transfer characteristics of lead-bismuth eutectic in circular tubes[J]. Applied Thermal Engineering, 180, 115820(2020).

    [9] Chen Y T, Zhang D L, Liang Y et al. Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation[J]. Annals of Nuclear Energy, 161, 108452(2021).

    [10] Liu Z P, Huang D S, Wang C L et al. Flow and heat transfer analysis of lead-bismuth eutectic flowing in a tube under rolling conditions[J]. Nuclear Engineering and Design, 382, 111373(2021).

    [11] Dong Z Y, Qiu H R, Wang M J et al. Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR)[J]. Annals of Nuclear Energy, 174, 109176(2022).

    [12] Zhu R S, Chen Y M, Lu Y G et al. Research on structure selection and design of LBE-cooled fast reactor main coolant pump[J]. Nuclear Engineering and Design, 371, 110973(2021).

    [13] Jeong J H, Kweon Y C. The effect of tube rupture location on the consequences of multiple steam generator tube rupture event[J]. Annals of Nuclear Energy, 29, 1809-1826(2002).

    [14] Yang Y P, Li Y, Wang C L et al. Parametric sensitivity analysis of liquid metal helical coil once-through tube steam generator[J]. Nuclear Engineering and Design, 383, 111427(2021).

    [15] 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).

    [16] Huang W L, Zhou D N, Sa R Y et al. Experimental study on thermal-hydraulic behaviour of LBE and water interface[J]. Progress in Nuclear Energy, 99, 1-10(2017).

    [17] Huang X, Chen P, Yin Y et al. Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors[J]. Nuclear Engineering and Design, 361, 110567(2020).

    [18] Iskhakov A S, Melikhov V I, Melikhov O I. Hugoniot analysis of energetic molten lead-water interaction[J]. Annals of Nuclear Energy, 129, 437-449(2019).

    [19] Pesetti A, Del Nevo A, Forgione N. Experimental investigation and SIMMER-III code modelling of LBE-water interaction in LIFUS5/Mod2 facility[J]. Nuclear Engineering and Design, 290, 119-126(2015).

    [20] Yu Q F, Zhang Y, Wang C L et al. Numerical simulation of bubble transport during steam generator tube rupture accident of lead-cooled fast reactor[J]. Annals of Nuclear Energy, 153, 108066(2021).

    [21] Zhang C D, Sa R Y, Zhou D N et al. Effects of failure location and pressure on the core voiding under SGTR accident in a LBE-cooled fast reactor[J]. International Journal of Heat and Mass Transfer, 141, 940-948(2019).

    [22] FENG Xiqiao, HE Shuyan, DONG Duo. Leak before break analysis of pipes and vessels in nuclear reactors[J]. Advances in Mechanics, 28, 198-217(1998).

    [23] Shen C, Liu L M, Xu Z Y et al. Influence of helix angle on flow and heat transfer characteristics of lead-bismuth flow in helical-coiled tube bundles[J]. Annals of Nuclear Energy, 180, 109483(2023).

    [24] Brackbill J U, Kothe D B, Zemach C. A continuum method for modeling surface tension[J]. Journal of Computational Physics, 100, 335-354(1992).

    [25] Rider W J, Kothe D B. Reconstructing volume tracking[J]. Journal of Computational Physics, 141, 112-152(1998).

    [26] Ju H M, Huang Z Y, Xu Y H et al. Hydraulic performance of small bending radius helical coil-pipe[J]. Journal of Nuclear Science and Technology, 38, 826-831(2001).

    [27] ZHU Hongye, YANG Xingtuan, JU Huaiming et al. Numerical analysis of heat transfer characteristics of helium flow cross helically coiled tube bundle[J]. Journal of Thermal Science and Technology, 11, 216-221(2012).

    [28] Kusunoki T, Odano N, Yoritsune T et al. Design of advanced integral-type marine reactor, MRX[J]. Nuclear Engineering and Design, 201, 155-175(2000).

    [29] Gokhale A M. Estimation of bivariate size and orientation distribution of microcracks[J]. Acta Materialia, 44, 475-485(1996).

    [30] Bernardin J D, Mudawar I, Walsh C B et al. Contact angle temperature dependence for water droplets on practical aluminum surfaces[J]. International Journal of Heat and Mass Transfer, 40, 1017-1033(1997).

    Weijian DONG, Tenglong CONG, Junzhi ZHU, Yao XIAO, Xumao ZOU, Hanyang GU. Numerical simulation of steam bubble dynamics at microcrack in LBE descending flow field[J]. NUCLEAR TECHNIQUES, 2022, 45(12): 120605
    Download Citation