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Volume 46 Issue 3
Jun.  2025
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Tang Simiao, Lian Qiang, Zhu Longxiang, Zhang Luteng, Ma Zaiyong. Research on Thermoelectric Coupling Characteristics of a 100 kW Silent Heat Pipe Cooled Reactor Based on Finite Element Method[J]. Nuclear Power Engineering, 2025, 46(3): 68-77. doi: 10.13832/j.jnpe.2024.060015
Citation: Tang Simiao, Lian Qiang, Zhu Longxiang, Zhang Luteng, Ma Zaiyong. Research on Thermoelectric Coupling Characteristics of a 100 kW Silent Heat Pipe Cooled Reactor Based on Finite Element Method[J]. Nuclear Power Engineering, 2025, 46(3): 68-77. doi: 10.13832/j.jnpe.2024.060015

Research on Thermoelectric Coupling Characteristics of a 100 kW Silent Heat Pipe Cooled Reactor Based on Finite Element Method

doi: 10.13832/j.jnpe.2024.060015
  • Received Date: 2024-06-04
  • Rev Recd Date: 2024-07-05
  • Available Online: 2025-06-09
  • Publish Date: 2025-06-09
  • The silent heat pipe reactor adopts a energy transmission and thermoelectric conversion system that couples high-temperature heat pipes with thermoelectric power generation. It is a preferred reactor type of portable small nuclear power source in various fields such as sea, land, air, and space in the future due to its passive safety, high reliability and ultra silence. Based on the multi physical field coupling analysis platform COMSOL Multiphysics, this paper establishes a quarter model of the whole system of the heat pipe reactor according to the design scheme of a 100-kilowatt level silent heat pipe reactor, including fuel rods, core matrix, heat pipes, reflectors, control rods, sliding reflectors, thermoelectric generations and other systems. Steady-state operating conditions, single heat pipe failure conditions, and single-row thermoelectric system unloading conditions are analyzed to investigate system thermoelectric coupling characteristics. The research results indicate that due to the temperature flattening characteristics of the core matrix and the thermoelectric system matrix, the failure of a single heat pipe will not have a significant impact on the operation of the reactor and the output power of the thermoelectric system. When the local thermoelectric system unloading accident occurs in a heat pipe reactor, the core temperature will increase due to the decrease in the heat transfer capacity of the thermoelectric system. The thermoelectric system that has not been unloaded can still work normally, ensuring effective electrical energy output.

     

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  • [1]
    GUO K L, ZHANG Y, LIN X Y, et al. Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER)[J]. Annals of Nuclear Energy, 2023, 189: 109818. doi: 10.1016/j.anucene.2023.109818
    [2]
    SUN H, MA P, LIU X, et al. Conceptual design and analysis of a multipurpose micro nuclear reactor power source[J]. Annals of Nuclear Energy, 2018, 121: 118-127. doi: 10.1016/j.anucene.2018.07.025
    [3]
    TANG S M, LIU X, WANG C L, et al. Thermal-electrical coupling characteristic analysis of the heat pipe cooled reactor with static thermoelectric conversion[J]. Annals of Nuclear Energy, 2022, 168: 108870. doi: 10.1016/j.anucene.2021.108870
    [4]
    TANG S M, WANG C L, ZHANG D L, et al. Thermoelectric performance study on a heat pipe thermoelectric generator for micro nuclear reactor application[J]. International Journal of Energy Research, 2021, 45(8): 12301-12316. doi: 10.1002/er.6450
    [5]
    PETERSON P F. Multiple-reheat Brayton cycles for nuclear power conversion with molten coolants[J]. Nuclear Technology, 2003, 144(3): 279-288. doi: 10.13182/NT144-279
    [6]
    DAI Z W, WANG C L, ZHANG D L, et al. Design and analysis of a free-piston stirling engine for space nuclear power reactor[J]. Nuclear Engineering and Technology, 2021, 53(2): 637-646. doi: 10.1016/j.net.2020.07.011
    [7]
    WANG C L, ZHANG R, GUO K L, et al. Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle[J]. Frontiers in Energy, 2021, 15(4): 916-929. doi: 10.1007/s11708-021-0757-9
    [8]
    ZHANG R, GUO K L, WANG C L, et al. Thermal-hydraulic analysis of gas-cooled space nuclear reactor power system with closed Brayton cycle[J]. International Journal of Energy Research, 2021, 45(8): 11851-11867. doi: 10.1002/er.5813
    [9]
    MCCLURE P R, POSTON D I, GIBSON M A, et al. Kilopower project: the KRUSTY fission power experiment and potential missions[J]. Nuclear Technology, 2020, 206(S1): S1-S12.
    [10]
    余红星,马誉高,张卓华,等. 热管冷却反应堆的兴起和发展[J]. 核动力工程,2019, 40(4): 1-8.
    [11]
    WANG C L, SUN H, TANG S M, et al. Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system[J]. Nuclear Engineering and Technology, 2020, 52(1): 19-26.
    [12]
    ZHANG W W, ZHANG D L, WANG C L, et al. Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system[J]. Annals of Nuclear Energy, 2020, 144: 107576. doi: 10.1016/j.anucene.2020.107576
    [13]
    LIU X, ZHANG R, LIANG Y, et al. Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor[J]. Annals of Nuclear Energy, 2020, 142: 107412. doi: 10.1016/j.anucene.2020.107412
    [14]
    ZHANG Z Q, CHAI X M, WANG C L, et al. Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor[J]. Nuclear Engineering and Design, 2021, 378: 111180. doi: 10.1016/j.nucengdes.2021.111180
    [15]
    MA Y G, LIU J S, YU H X, et al. Coupled irradiation-thermal-mechanical analysis of the solid-state core in a heat pipe cooled reactor[J]. Nuclear Engineering and Technology, 2022, 54(6): 2094-2106. doi: 10.1016/j.net.2022.01.002
    [16]
    TANG S M, LIAN Q, ZHU L X, et al. Thermal-electrical coupling analysis of the static heat pipe cooled reactor under heat pipe failure condition[J]. Nuclear Engineering and Design, 2024, 417: 112812. doi: 10.1016/j.nucengdes.2023.112812
    [17]
    ZHANG Y, GUO K L, WANG C L, et al. Numerical analysis of segmented thermoelectric generators applied in the heat pipe cooled nuclear reactor[J]. Applied Thermal Engineering, 2022, 204: 117949. doi: 10.1016/j.applthermaleng.2021.117949
    [18]
    HUANG J L, WANG C L, TIAN Z X, et al. Preliminary conceptual design and analysis of a 100 kWe level Nuclear Silent Thermal-Electrical Reactor (NUSTER-100)[J]. International Journal of Energy Research, 2022, 46(14): 19653-19666. doi: 10.1002/er.8542
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