An Investigation of Structural Strength of Nuclear Fuel Spacer Grid

Author:

Adli Naqeeb Hakam1,Namgung Ihn1

Affiliation:

1. KEPCO International Nuclear Graduate School, Ulsan 45014, Republic of Korea

Abstract

This paper compares and discusses the methods for evaluation of the structural integrity of the mid spacer grid of nuclear fuel assembly via a finite element analysis of 3D shell elements. The structural stiffness of the spacer grid is determined by applying either force or deformation as loads onto the spacer grid for both the square load and shear load directions. This study is an extension of a single-cell strength analysis of a spacer. External events such as seismic activities that might happen in a nuclear reactor are able to transfer loads onto nuclear components in random directions, which can be broken down into square and shear loadings. The structural strength indicated by the force reaction against the input displacement load was proven to be smaller such that the same displacement square load is around 260 times greater than the shear load. Due to the weakness in shear stiffness, the maintenance of a spacer grid structure is more vulnerable against out-of-plane loads. This indicates that the shear load needs to be considered in studies of fuel assembly integrity assessment for newly developing fuel design, as well as existing fuel assembly designs.

Funder

National Research Fund

Publisher

MDPI AG

Reference19 articles.

1. Development of nuclear fuel assembly 3D reduced model and modal analysis;Subhan;Ann. Nucl. Energy,2023

2. ASME (2021). ASME Boiler and Pressure Vessel Code, Section III, Non-Mandatory Appendix F, Rules for Evaluation of Service Loadings with Level D Service Limits, American Society of Mechanical Engineers.

3. An investigation of structural strength of PWR fuel assembly spacer grid with fuel rod clad;Namgung;Ann. Nucl. Energy,2024

4. New spacer grid to enhance mechanical/structural performance;Song;Nucl. Sci. Technol.,2010

5. Finite element analysis of the mechanical behavior of a nuclear fuel assembly spacer grid;Yoo;Nucl. Eng. Des.,2019

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