• NUCLEAR TECHNIQUES
  • Vol. 45, Issue 11, 110601 (2022)
Siqin HU1、2, Jian TIAN1、*, Chong ZHOU1, Yang ZOU1, and Xiaohan YU1
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.0253-3219.2022.hjs.45.110601 Cite this Article
    Siqin HU, Jian TIAN, Chong ZHOU, Yang ZOU, Xiaohan YU. Optimal design of core flow distribution for 10 MW liquid fuel molten salt reactor[J]. NUCLEAR TECHNIQUES, 2022, 45(11): 110601 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] 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).

    [3] Yu C G, Li X X, Cai X Z et al. Analysis of minor actinides transmutation for a molten salt fast reactor[J]. Annals of Nuclear Energy, 85, 597-604(2015).

    [4] YU Pingan, ZHU Ruian, YU Zhenwan et al[M]. Nuclear reactor thermal analysis, 146-148(2002).

    [5] ZHOU Zhenhua, PAN Deng, CHEN Yushuang et al. Core flow distribution design of molten salt reactor with liquid fuel[J]. Nuclear Techniques, 39, 050601(2016).

    [6] Bhatnagar V, Deffrennes M, Hugon M et al. FISA-2009 conference on euratom research and training activities: nuclear fission - past, present and future (generation-II, -III and -IV + partitioning and transmutation)[J]. Nuclear Engineering and Design, 241, 3376-3388(2011).

    [7] LeBlanc D. Molten salt reactors: a new beginning for an old idea[J]. Nuclear Engineering and Design, 240, 1644-1656(2010).

    [8] YANG Laisheng, ZONG Guifang, HU Jun. Reactor hydraulic simulation test study of Qinshan phase Ⅱ NPP project[J]. Nuclear Power Engineering, 24, 208-211, 226(2003).

    [9] TANG Mao, ZHANG Mingqian, CHEN Liang et al. Numerical analysis of flow skirt influence on core inlet flow distribution[J]. Nuclear Power Engineering, 34, 83-86(2013).

    [10] ZHANG Mingqian, DUAN Yuangang, ZHU Mingli et al. Optimized design for the flow distribution device of nuclear reactor internals based on CFD simulation[J]. Nuclear Science and Engineering, 35, 193-199(2015).

    [11] Zhou J J, Guo Z P, Qiu S Z et al. The influence of lower plenum and distribution plates to thermal hydraulics characteristics of MSR[J]. Nuclear Engineering and Design, 256, 235-248(2013).

    [12] WEN Jun, PENG Tianji, FAN Xukai et al. Analysis and optimization of flow distribution for the reactor core of China initiative accelerator driven systemFull text replacement[J]. Nuclear Techniques, 43, 070601(2020).

    [13] WANG Tianshi, ZHAO Pengcheng, LIU Zijing et al. Study on the influence of the geometry of the primary circuit plenum on the core flow distribution characteristics of the natural circulation lead-based fast reactor[J]. Nuclear Techniques, 43, 030602(2020).

    [14] Bajorek S M. NRC confirmatory analysis and advancednon-LWR code selection[C].

    [15] Rouch H, Geoffroy O, Rubiolo P et al. Preliminary thermal-hydraulic core design of the Molten Salt Fast Reactor (MSFR)[J]. Annals of Nuclear Energy, 64, 449-456(2014).

    [16] Podila K, Chen Q, Rao Y F. CFD simulations of molten salt reactor experiment core[J]. Nuclear Science and Engineering, 193, 1379-1393(2019).

    [17] ZHENG Jiantao, LI Huaqi. Numerical study on effects of shroud in core lower plenum on flow field[J]. Nuclear Power Engineering, 36, 148-151(2015).

    Siqin HU, Jian TIAN, Chong ZHOU, Yang ZOU, Xiaohan YU. Optimal design of core flow distribution for 10 MW liquid fuel molten salt reactor[J]. NUCLEAR TECHNIQUES, 2022, 45(11): 110601
    Download Citation