• High Power Laser and Particle Beams
  • Vol. 34, Issue 2, 026019 (2022)
Kunfeng Ma and Po Hu*
Author Affiliations
  • School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China
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    DOI: 10.11884/HPLPB202234.210388 Cite this Article
    Kunfeng Ma, Po Hu. Depletion calculation of heat pipe cooled nuclear reactor with different monolithic materials[J]. High Power Laser and Particle Beams, 2022, 34(2): 026019 Copy Citation Text show less
    References

    [1] Wang D Q, Yan B H, Chen J Y. The opportunities and challenges of micro heat piped cooled reactor system with high efficiency energy conversion units[J]. Annals of Nuclear Energy, 149, 107808(2020).

    [2] Yan B H, Wang C, Li L G. The technology of micro heat pipe cooled reactor: A review[J]. Annals of Nuclear Energy, 135, 106948(2020).

    [3] McClure P R, Poston D I, Dasari V R, et al. Design of megawatt power level heat pipe reacts[R]. LAUR1528840, 2015.

    [4] Sterbentz J W, Werner J E, McKellar M G, et al. Special purpose nuclear react (5 MW) f reliable power at remote sites assessment rept [R]. INLEXT1640741, 2017.

    [5] Ma Y G, Chen E H, Yu H X, et al. Heat pipe failure accident analysis in megawatt heat pipe cooled reactor[J]. Annals of Nuclear Energy, 149, 107755(2020).

    [7] Ma Y G, Liu M Y, Xie B H, et al. Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods[J]. Annals of Nuclear Energy, 151, 107923(2021).

    [8] 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, 144, 107576(2020).

    [9] Sun H, Wang C L, Ma P, et al. Conceptual design analysis of a multipurpose micro nuclear react power source[J]. Annals of Nuclear Energy, 2018, 121: 118–127.

    [10] Khandaq M F, Harto A W, Agung A W. Conceptual core design study for Indonesian Space Reactor (ISR)[J]. Progress in Nuclear Energy, 118, 103109(2020).

    [12] Li W, Shirven S. Implications of SiC irradiation creep and annealing to UN-SiC fuel rod behavior[J]. Journal of Nuclear Materials, 542, 152479(2020).

    [13] Herrmann M, Meisel P, Lippmann W, et al. Joining technology—A challenge for the use of SiC components in HTRs[J]. Nuclear Engineering and Design, 306, 170-176(2016).

    [14] Hernez R, Todosow M, Brown N R. Micro heat pipe nuclear react concepts: Analysis of fuel cycle perfmance environmental impacts[J]. Annals of Nuclear Energy, 2019, 126: 419426.

    [15] Wang K, Li Z G, She D, et al. RMC-A Monte Carlo code for reactor core analysis[J]. Annals of Nuclear Energy, 82, 121-129(2015).

    [16] Ma Y G, Liu S C, Luo Z, et al. RMC/CTF multiphysics solutions to VERA core physics benchmark problem 9[J]. Annals of Nuclear Energy, 133, 837-852(2019).

    [17] Chadwick M B, Obloˇzinsk´y P, Herman M, et al. ENDF/B-VII. 0: Next generation evaluated nuclear data library for nuclear science and technology[J]. Nuclear Data Sheets, 107, 2931-3060(2006).

    [18] Zhang A, Zou C Y, Wu J H, et al. Radiotoxicity of minor actinides in thermal, epithermal and fast TMSRs with very high burnup[J]. Annals of Nuclear Energy, 137, 107162(2020).

    [19] Liu B, Wang K, Tu J, et al. Transmutation of minor actinides in the pressurized water reactors[J]. Annals of Nuclear Energy, 64, 86-92(2014).

    Kunfeng Ma, Po Hu. Depletion calculation of heat pipe cooled nuclear reactor with different monolithic materials[J]. High Power Laser and Particle Beams, 2022, 34(2): 026019
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