• NUCLEAR TECHNIQUES
  • Vol. 47, Issue 8, 080602 (2024)
Mudan MEI1,2, Chong ZHOU1,2,*, Yao FU1,2, Yang ZOU1,2, and Naxiu WANG1,2
Author Affiliations
  • 1Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
  • 2University of Chinese Academy of Sciences, Beijing 100049, China
  • show less
    DOI: 10.11889/j.0253-3219.2024.hjs.47.080602 Cite this Article
    Mudan MEI, Chong ZHOU, Yao FU, Yang ZOU, Naxiu WANG. Optimal design of passive cooling system for the reactor lower cavity of molten salt reactor[J]. NUCLEAR TECHNIQUES, 2024, 47(8): 080602 Copy Citation Text show less
    References

    [1] JIANG Mianheng, XU Hongjie, DAI Zhimin. Advanced fission energy program-TMSR nuclear energy system[J]. Bulletin of Chinese Academy of Sciences, 27, 366-374(2012).

    [2] CAI Xiangzhou, DAI Zhimin, XU Hongjie. Thorium molten salt reactor nuclear energy system[J]. Physics, 45, 578-590(2016).

    [3] Xu H J, Dai Z M, Cai X Z. Some physical issues of the thorium molten salt reactor nuclear energy system[J]. Nuclear Physics News, 24, 24-30(2014).

    [4] Shen X C, Fu Y, Zhang J Y. Study on the effect of thermal deformation on the liquid seal of high-temperature molten salt pump in molten salt reactor[J]. Nuclear Science and Techniques, 34, 27(2023).

    [5] Chen C Q, Xia X B, Zhang Z H et al. Radiological environmental impact analysis of a 2-MW thorium molten salt reactor during an accident[J]. Nuclear Science and Techniques, 30, 78(2019).

    [6] Liu Y B, Meng X Y, Wang X S et al. Transient analysis and optimization of passive residual heat removal heat exchanger in advanced nuclear power plant[J]. Nuclear Science and Techniques, 33, 106(2022).

    [7] Wang C L, Qin H, Zhang D L et al. Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors[J]. Nuclear Science and Techniques, 31, 65(2020).

    [8] YU Ping'an, ZHU Ruian, YU Zhenwan et al[M]. Thermal analysis of nuclear reactors(2002).

    [9] Zhao H B, Chen X M, Zheng Y H et al. Three-dimensional numerical investigation of heat transfer process in the reactor cavity of HTR-10[J]. Annals of Nuclear Energy, 114, 551-560(2018).

    [10] LI Xiaowei, WU Xinxin, ZHANG Li et al. Analysis of passive residual heat removal system of modular high temperature gas-cooled reactor[J]. Atomic Energy Science and Technology, 45, 790-795(2011).

    [11] HE Dongyu, SUN Ximing. Numerical analysis of natural convection in HTR-PM reactor cabin[J]. Atomic Energy Science and Technology, 45, 657-661(2011).

    [12] Park G C, Cho Y J, Cho H K. Assessment of a new design for a reactor cavity cooling system in a very high temperature gas-cooled reactor[J]. Nuclear Engineering and Technology, 38, 45-60(2006).

    [13] Frisani A, Hassan Y A. Computation fluid dynamics analysis of the reactor cavity cooling system for very high temperature gas-cooled reactors[J]. Annals of Nuclear Energy, 72, 257-267(2014).

    [14] HU Siqin, TIAN Jian, ZHOU Chong et al. Optimal design of core flow distribution for 10 MW liquid fuel molten salt reactor[J]. Nuclear Techniques, 45, 110601(2022).

    [15] Wang C L, Qin H, Zhang D L et al. Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors[J]. Nuclear Science and Techniques, 31, 65(2020).

    [16] WANG Yongping, TAO Yushan, WU Yunqin et al. Shielding design of a megawatt-scale heat pipe reactor core[J]. Nuclear Techniques, 46, 020606(2023).

    [17] Shen X C, Fu Y, Zhang J Y. Study on the effect of thermal deformation on the liquid seal of high-temperature molten salt pump in molten salt reactor[J]. Nuclear Science and Techniques, 34, 27(2023).

    [18] DENG Haofang, WANG Anqing, Xujian LYU. CFD based study of natural convection characteristics driven by buoyancy in containment[J]. Nuclear Techniques, 45, 090602(2022).

    [20] YANG Yang, ZOU Yang, CHEN Jingen et al. Flow and heat transfer characteristics of FLiNaK salt in an annular channel heater[J]. Nuclear Techniques, 45, 070604(2022).

    Mudan MEI, Chong ZHOU, Yao FU, Yang ZOU, Naxiu WANG. Optimal design of passive cooling system for the reactor lower cavity of molten salt reactor[J]. NUCLEAR TECHNIQUES, 2024, 47(8): 080602
    Download Citation