NUCLEAR TECHNIQUES, Volume. 47, Issue 12, 120601(2024)

Validation of the early in-vessel phenomenon analysis model of the severe accident analysis code MOSAP

Chao GUO1, Shihao WU2, Chuanqi ZHAO1, Yapei ZHANG2, Chao WEI1、*, and Yingwei WU2
Author Affiliations
  • 1Nuclear and Radiation Safety Center, Beijing 100082, China
  • 2Xi'an Jiaotong University, Xi'an 710049, China
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    Figures & Tables(16)
    Schematic diagram of CORA-13 experimental facility
    Diagram of CORA-13 bundle test section
    Node division of CORA-13 test section in MOSAP
    Temperature response at 550 mm of heated fuel rod (color online)
    Temperature response at 950 mm of heated fuel rod (color online)
    Comparison of hydrogen production amount (color online)
    Schematic diagram of Phebus FPT1 test circuit
    Axial dimension diagram of Phebus FPT1 fuel rod bundle
    Node division diagram of Phebus FPT1 test section in MOSAP
    Temperature response at 300 mm of fuel rod (color online)
    Temperature response at 400 mm of fuel rod (color online)
    Temperature response at 500 mm of control rod guide tube (color online)
    Comparison of hydrogen production amount (color online)
    Comparison of average system pressure (color online)
    Release rate comparisons of Xe (a), Cs (b), Ba (c), I (d), Te (e), Mo (f) (color online)
    • Table 1. Design parameters of CORA-13 test rod bundle

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      Table 1. Design parameters of CORA-13 test rod bundle

      部件Component材料Material参数Parameter值Value

      加热燃料棒Heated fuel rod

      非加热燃料棒Unheat rod

      UO2环形芯块Annular pellets

      UO2全芯块Full pellets

      长度Length / mm

      长度Length / mm

      1 960

      1 672

      燃料棒包壳Fuel rod claddingZr-4厚度Thickness / mm0.725

      U-235富集度U-235 enrichment

      吸收棒Absorber rod

      吸收棒包壳Absorber rod cladding

      吸收棒导向管Absorber rod guide tube

      栅格Spacer

      围板Shroud

      80%Ag+15%In+5%Cd

      不锈钢Stainless steel

      Zr-4

      Zr-4/ Inconel

      Zr-4

      长度Length / mm

      厚度Thickness / mm

      厚度Thickness / mm

      长度Length / mm

      厚度Thickness / mm

      0.2%

      1 660

      1

      0.8

      42/38

      1.2

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    Chao GUO, Shihao WU, Chuanqi ZHAO, Yapei ZHANG, Chao WEI, Yingwei WU. Validation of the early in-vessel phenomenon analysis model of the severe accident analysis code MOSAP[J]. NUCLEAR TECHNIQUES, 2024, 47(12): 120601

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Feb. 26, 2024

    Accepted: --

    Published Online: Jan. 15, 2025

    The Author Email: WEI Chao (WEIChao)

    DOI:10.11889/j.0253-3219.2024.hjs.47.120601

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