NUCLEAR TECHNIQUES, Volume. 47, Issue 8, 080605(2024)

Preliminary analysis of nuclear criticality safety of micro-reactor under high-speed impact

Lipeng WANG1、*, Lu CAO1, Lixin CHEN1, Rui LI2, Shichang LIU2, Da LI1, Xinyi ZHANG1, Duoyu JIANG1, Tianliang HU1, and Xinbiao JIANG1
Author Affiliations
  • 1Northwest Institute of Nuclear Technology, Xi'an 710024, China
  • 2School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China
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    Figures & Tables(19)
    Schematic diagram of coupled program workflow
    Geometric diagram of pure fuel reactor vertical impact with ground
    Yield surface of constitutive model of crushed foam model[15]
    Geometric diagram of cylinder reactor impact the ground at a 30° angle
    Density change in fuel vertical impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.001 2 s, (d) 0.001 5 s
    Normalized neutron flux change in fuel vertical impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.001 2 s, (d) 0.001 5 s
    Normalized heating change in fuel vertical impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.001 2 s, (d) 0.001 5 s
    Strain pressure change in fuel vertical impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.001 2 s, (d) 0.001 5 s
    Discrepancies in keff values for different codes under uniform density variation
    Criticality properties of fuel vertical impact with ground at different times
    Percentage difference in flux and heating distribution between uniform (a) and nonuniform (b) densities
    Density change in cylinder reactor under 30° impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.002 4 s, (d) 0.003 s
    Normalized thermal neutron flux change in cylinder reactor under 30° impact with ground(a) 0 s, (b) 0.001 05 s, (c) 0.002 4 s, (d) 0.003 s
    Normalized heating change in cylinder reactor 30° impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.002 4 s, (d) 0.003 s
    Strain pressure change in cylinder reactor under 30° impact with ground (a) 0 s, (b) 0.001 05 s, (c) 0.002 4 s, (d) 0.003 s
    Discrepancies in keff values for different codes under uniform density variation
    Criticality properties of cylinder reactor under 30° impact with ground at different times
    Difference in thermal neutron flux and heating distribution between uniform (a) and nonuniform density (b) of cylinder core
    • Table 1. Material data for ABAQUS

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      Table 1. Material data for ABAQUS

      材料

      Material

      弹性模量

      Elastic modulus / MPa

      泊松比

      Poisson ratio

      塑性硬化关系Hardening curve
      屈服应力Yield stress / MPa应变Strain
      不锈钢Stainless steel210 0000.3

      420

      830

      0
      0.15
      铝Al73 1000.3

      170

      340

      0
      0.1
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    Lipeng WANG, Lu CAO, Lixin CHEN, Rui LI, Shichang LIU, Da LI, Xinyi ZHANG, Duoyu JIANG, Tianliang HU, Xinbiao JIANG. Preliminary analysis of nuclear criticality safety of micro-reactor under high-speed impact[J]. NUCLEAR TECHNIQUES, 2024, 47(8): 080605

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    Paper Information

    Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

    Received: Sep. 14, 2023

    Accepted: --

    Published Online: Sep. 23, 2024

    The Author Email: WANG Lipeng (wang0214@126.com)

    DOI:10.11889/j.0253-3219.2024.hjs.47.080605

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