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Refinement of Finite Element Method Analysis Model of Pressurized Water Reactor Nuclear Fuel Spacer Grid Based on Experimental Data

Author

Listed:
  • Minhee Kim

    (Department of NPP Engineering, KEPCO International Nuclear Graduate School, Ulsan 45014, Republic of Korea)

  • Ihn Namgung

    (Department of NPP Engineering, KEPCO International Nuclear Graduate School, Ulsan 45014, Republic of Korea)

Abstract

A Finite Element Method (FEM) analysis of the nuclear fuel spacer grid was conducted to assess the strength of components for the safety of nuclear power plants. The fuel assembly consists of fuel rods, upper end-fitting, lower end-fitting, guide tubes, and spacer grids. Spacer grids play a critical role in maintaining the proper spacing between fuel rods within a fuel assembly and ensuring smooth coolant flow. This role becomes particularly crucial during unforeseen emergencies, such as seismic loads, where minimizing deformation caused by external forces is essential. Therefore, this study proposes FEM models of spacer grids, mesh refinement of models, and analysis of the stiffness of the spacer grids concerning the presence or absence of pellet and clad. The results revealed significantly lower shear stiffness compared to normal stiffness, indicating potential vulnerability of the fuel assembly to large loads such as those experienced during seismic events.

Suggested Citation

  • Minhee Kim & Ihn Namgung, 2025. "Refinement of Finite Element Method Analysis Model of Pressurized Water Reactor Nuclear Fuel Spacer Grid Based on Experimental Data," Energies, MDPI, vol. 18(3), pages 1-23, January.
    • Handle: RePEc:gam:jeners:v:18:y:2025:i:3:p:528-:d:1574876
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