NUCLEAR TECHNIQUES, Volume. 47, Issue 4, 040603(2024)

Analysis of fission product source term release and decay heat under pressurized water reactor rupture accident

Xianbao YUAN1,2, Jueqin PENG2,3, Binhang ZHANG2,3, Zhangliang MAO2,3、*, Haibo TANG2,3, Jingyu WEI2,3, and Jianjun ZHOU2,3
Author Affiliations
  • 1College of Science,China There Gorges University, Yichang 443002, China
  • 2College of Mechanical and Power Engineering, China There Gorges University, Yichang 443002, China
  • 3Hubei Key Laboratory of Hydroelectric Machinery Design & Maintenance, China There Gorges University, Yichang 443002, China
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    Figures & Tables(22)
    Nodalization of primary loop system 1. Core, 2. Upper plenum, 3. Broken hot leg, 4,10. Hot leg steam generator shell, 5,11. Cold leg steam generator shell, 6,12. Intermediate leg, 7,13. Cold leg, 8. Downcomer, 9. Unbroken hot leg, 14. Reactor dome
    Nodal division of containment 1. Cavity, 2. Lower compartment, 3. Upper compartment, 4. Annular compartment, 5. External environment
    Flow chart of program calculation
    Flux of reactor primary loop
    Mass of molten material in pressure vessel
    Pressure variation curve of containment
    Mass released from fission product source term in-vessel (a) CORSOR-M model, (b) CORSOR-O model, (c) ORNL-BOOTH model
    Masses released from fission product source terms ex-vessel(a) CORSOR-M model, (b) CORSOR-O model, (c) ORNL-BOOTH model
    Spray-on mass of molten material in pressure vessel
    Spray-on containment pressure change curve
    Spray-off variation curve of suspended iodide CsI
    Spray-on variation curve of suspended iodide CsI
    Spray-on variation curve of deposited iodide CsI
    Spray-off variation curve of fission gas
    Spray-on variation curve of fission gas
    Fraction of decay heat generated by the source term over the total decay heat fraction
    Spray-off decay heat of fission product components (a) CORSOR-M model, (b) CORSOR-O model (c) ORNL-BOOTH model
    Spray-on total decay heat of fission products (color online)
    • Table 1. Comparison of steady state operating parameters

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      Table 1. Comparison of steady state operating parameters

      主要参数

      Main parameters

      建模参数值

      Modeling parameter values

      稳态运行值

      Steady state value

      误差

      Inaccuracies / %

      堆芯额定输出功率Core rated output power / MW2 895.002 902.000.20
      堆芯进口温度Core inlet temperature / K565.55564.900.10
      堆芯出口温度Core outlet temperature / K602.95601.000.30
      稳压器顶部压力Pressure at the top of the regulator / MPa15.5014.854.10
      稳压器水位Pressure regulator water level / m7.397.202.50
      S/G主蒸汽压力S/G main steam pressure / MPa6.706.801.50
      S/G主蒸汽温度S/G main steam temperature / K556.00557.800.30
    • Table 2. Grouping of fission products

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      Table 2. Grouping of fission products

      组分(ik)

      Components

      化合物

      Chemical compound

      1Nobles
      2CsI, RbI
      3TeO2
      4SrO
      5MoO2, RuO2, RhO2
      6CsOH, RbOH
      7BaO
      8La2O3, Pr2O3, Nd2O3, Sm2O3, Y2O3
      9CeO2, NpO2, PuO2
      10Sb
      11Te2
      12UO2
      13Ag, Cd, In, Ag, Sn, Mn
    • Table 3. Accident sequence (s)

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      Table 3. Accident sequence (s)

      主要事件Main eventsCORSOR-MCORSOR-OORNL-BOOTH
      高压安注、低压安注关闭 HPI, LPI pump switch forced off0.010.010.01
      安全壳喷淋关闭 Spray pump switch forced off0.010.010.01
      裂变产物释放模型开启 Fission products model on19.8519.8519.85
      反应堆停堆 Reactor scram26.7626.7626.76
      堆芯裸露 Core has uncovered.698.52698.52698.52

      堆芯最高温度超过2 499 K

      Maximum core temperature has exceeded 2 499 K

      4 560.194 560.184 559.92
      堆芯熔融物向下封头移动 Relocation of core materials to lower head started5 925.105 887.015 908.32
      压力容器失效 Pressure vessel failed11 156.5911 189.8411 105.06
      安全壳失效 Containment failed217 378.79187 168.50227 022.32
    • Table 4. Accident sequence (s)

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      Table 4. Accident sequence (s)

      主要事件Main eventsCORSOR-MCORSOR-OORNL-BOOTH
      事故发生Accident occurred0.010.010.01
      反应堆停堆Reactor scram26.7626.7626.76
      喷淋启动Spray pump switch forced on724.43724.43724.43

      堆芯熔融物向下封头移动

      Relocation of core materials to lower head started

      5 854.295 825.905 831.35
      压力容器失效Pressure vessel failed11 335.4711 307.6711 011.52
      计算结束End of calculation300 000.00300 000.00300 000.00
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    Xianbao YUAN, Jueqin PENG, Binhang ZHANG, Zhangliang MAO, Haibo TANG, Jingyu WEI, Jianjun ZHOU. Analysis of fission product source term release and decay heat under pressurized water reactor rupture accident[J]. NUCLEAR TECHNIQUES, 2024, 47(4): 040603

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    Paper Information

    Category: Research Articles

    Received: Aug. 10, 2023

    Accepted: --

    Published Online: May. 28, 2024

    The Author Email: MAO Zhangliang (毛璋亮)

    DOI:10.11889/j.0253-3219.2024.hjs.47.040603

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