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Investigation into the In-box LOCA of water cooled solid breeder blanket for CFETR based on PWR conditions

  • School of Nuclear Science and Technology,University of Science and Technology of China,Hefei 230022,China

Cite this:
https://doi.org/10.3969/j.issn.0253-2778.2017.06.005
  • Received Date: 28 September 2016
  • Rev Recd Date: 07 November 2016
  • Publish Date: 30 June 2017
    Abstract

  • Abstract

    China Fusion Engineering Testing Reactor（CFETR）is an “ITER-like” DEMO fusion reactor in China. As one of the breeding blanket candidates for CFETR, a water cooled breeder blanket based on PWR conditions has been designed. Here In-box LOCA of water cooled solid breeder blanket for CFETR based on PWR conditions was investigated by RELAP5/MOD3.4. The accident’s processes were described in detail and its results were analyzed preliminarily.According to the computational results, first wall (FW) does not melt and the production of hydrogen is lower than the limit. Meanwhile, due to the rupture disk, the flow can vent into the vacuum vessel(VV) after the accident, which ensures the integrity of the blanket. And due to the large volume of the VV, the final pressure of VV is much lower than the limit.

    Abstract

    China Fusion Engineering Testing Reactor（CFETR）is an “ITER-like” DEMO fusion reactor in China. As one of the breeding blanket candidates for CFETR, a water cooled breeder blanket based on PWR conditions has been designed. Here In-box LOCA of water cooled solid breeder blanket for CFETR based on PWR conditions was investigated by RELAP5/MOD3.4. The accident’s processes were described in detail and its results were analyzed preliminarily.According to the computational results, first wall (FW) does not melt and the production of hydrogen is lower than the limit. Meanwhile, due to the rupture disk, the flow can vent into the vacuum vessel(VV) after the accident, which ensures the integrity of the blanket. And due to the large volume of the VV, the final pressure of VV is much lower than the limit.
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    • References(15)
  • [1]
    LI J G.Closing gaps to CFETR readiness[C]// IAEA TCM 3rd DEMO Workshop, Hefei, China. 2015: 11-14.
    [2]
    LIU S, PU Y, CHENG X, et al. Conceptual design of a water cooled breeder blanket for CFETR[J]. Fusion Engineering and Design, 2014, 89(7): 1380-1385.
    [3]
    AHN M Y, CHO S, KIM D H, et al. Preliminary safety analysis of Korea helium cooled solid breeder test blanket module[J]. Fusion Engineering and Design, 2008, 83(10): 1753-1758.
    [4]
    LEE D W, JIN H G, SHIN K I, et al. Investigation into the In-box LOCA consequence and structural integrity of the KO HCCR TBM in ITER[J]. Fusion Engineering and Design, 2014, 89(7): 1177-1180.
    [5]
    JIN H G, LEE D W, LEE E H, et al. Sensitivity study on In-box LOCA for a Korean HCCR TBM in ITER[J]. Fusion Engineering and Design, 2014, 89(9): 2024-2027.
    [6]
    BOCCACCINI L V, CIATTAGLIA S, MEYDER R, et al. Review of accidental safety studies for the European HCPB test blanket system[J]. Nuclear fusion, 2007, 47(7): S436.
    [7]
    李伟, 田文喜, 秋穗正, 等. 基于 RELAP5 的双功能液态锂铅实验包层模块安全分析[J]. 原子能科学技术, 2013, 47(11): 2046-2052.
    LI Wei, TIAN Wenxi, QIU Suizheng, et al. Safety analysis on dual-functional lithium lead test blanket module with RELAP5[J]. Atomic Energy Science and Technology, 2013, 47(11): 2046-2052.
    [8]
    WANG J, TIAN W, SU G, et al. Thermal-hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system[J]. Fusion Engineering and Design, 2013, 88(1): 33-41.
    [9]
    AHN M Y, CHO S, KU D Y, et al. LOCA analysis for Korean helium cooled solid breeder TBM[J]. Fusion Engineering and Design, 2009, 84(2): 380-384.
    [10]
    WANG S, ZHOU G, LV Z, et al. Design and safety analysis of the helium cooled solid breeder blanket for CFETR[J]. Kerntechnik, 2016, 81(2): 192-196.
    [11]
    AHN M Y, JIN H G, CHO S, et al. Current status of accident analysis for Korean HCCR TBS[J]. Fusion Engineering and Design, 2014, 89(7): 1289-1293.
    [12]
    JIN X, BOCCACCINI L V, MEYDER R. Deterministic safety analysis of the reference accidental sequence for the European HCPB TBM system[J]. Fusion Engineering and Design, 2008, 83(10): 1759-1763.
    [13]
    ANDERL R A, MCCARTHY K A, OATES M A, et al. Steam-chemical reactivity for irradiated beryllium[J]. Journal of Nuclear Materials, 1998, 258: 750-756.
    [14]
    ANDERL R A, SCAFFIDI-ARGENTINA F, DAVYDOV D, et al. Steam chemical reactivity of Be pebbles and Be powder[J]. Journal of Nuclear Materials, 2000, 283: 1463-1467.
    [15]
    JIN X Z, MERRILL B J, BOCCACCINI L V. Preliminary safety analysis of ex-vessel LOCA for the European HCPB TBM system[J]. Fusion Engineering and Design, 2012, 87(5): 454-460.
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    [1]
    LI J G.Closing gaps to CFETR readiness[C]// IAEA TCM 3rd DEMO Workshop, Hefei, China. 2015: 11-14.
    [2]
    LIU S, PU Y, CHENG X, et al. Conceptual design of a water cooled breeder blanket for CFETR[J]. Fusion Engineering and Design, 2014, 89(7): 1380-1385.
    [3]
    AHN M Y, CHO S, KIM D H, et al. Preliminary safety analysis of Korea helium cooled solid breeder test blanket module[J]. Fusion Engineering and Design, 2008, 83(10): 1753-1758.
    [4]
    LEE D W, JIN H G, SHIN K I, et al. Investigation into the In-box LOCA consequence and structural integrity of the KO HCCR TBM in ITER[J]. Fusion Engineering and Design, 2014, 89(7): 1177-1180.
    [5]
    JIN H G, LEE D W, LEE E H, et al. Sensitivity study on In-box LOCA for a Korean HCCR TBM in ITER[J]. Fusion Engineering and Design, 2014, 89(9): 2024-2027.
    [6]
    BOCCACCINI L V, CIATTAGLIA S, MEYDER R, et al. Review of accidental safety studies for the European HCPB test blanket system[J]. Nuclear fusion, 2007, 47(7): S436.
    [7]
    李伟, 田文喜, 秋穗正, 等. 基于 RELAP5 的双功能液态锂铅实验包层模块安全分析[J]. 原子能科学技术, 2013, 47(11): 2046-2052.
    LI Wei, TIAN Wenxi, QIU Suizheng, et al. Safety analysis on dual-functional lithium lead test blanket module with RELAP5[J]. Atomic Energy Science and Technology, 2013, 47(11): 2046-2052.
    [8]
    WANG J, TIAN W, SU G, et al. Thermal-hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system[J]. Fusion Engineering and Design, 2013, 88(1): 33-41.
    [9]
    AHN M Y, CHO S, KU D Y, et al. LOCA analysis for Korean helium cooled solid breeder TBM[J]. Fusion Engineering and Design, 2009, 84(2): 380-384.
    [10]
    WANG S, ZHOU G, LV Z, et al. Design and safety analysis of the helium cooled solid breeder blanket for CFETR[J]. Kerntechnik, 2016, 81(2): 192-196.
    [11]
    AHN M Y, JIN H G, CHO S, et al. Current status of accident analysis for Korean HCCR TBS[J]. Fusion Engineering and Design, 2014, 89(7): 1289-1293.
    [12]
    JIN X, BOCCACCINI L V, MEYDER R. Deterministic safety analysis of the reference accidental sequence for the European HCPB TBM system[J]. Fusion Engineering and Design, 2008, 83(10): 1759-1763.
    [13]
    ANDERL R A, MCCARTHY K A, OATES M A, et al. Steam-chemical reactivity for irradiated beryllium[J]. Journal of Nuclear Materials, 1998, 258: 750-756.
    [14]
    ANDERL R A, SCAFFIDI-ARGENTINA F, DAVYDOV D, et al. Steam chemical reactivity of Be pebbles and Be powder[J]. Journal of Nuclear Materials, 2000, 283: 1463-1467.
    [15]
    JIN X Z, MERRILL B J, BOCCACCINI L V. Preliminary safety analysis of ex-vessel LOCA for the European HCPB TBM system[J]. Fusion Engineering and Design, 2012, 87(5): 454-460.
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