Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Effect of initial coating crack on the mechanical performance of surface-coated zircaloy cladding

  • Xu, Ze (Department of Applied Mechanics and Engineering, Sun Yat-Sen University) ;
  • Liu, Yulan (Department of Applied Mechanics and Engineering, Sun Yat-Sen University) ;
  • Wang, Biao (Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University)
  • Received : 2020.06.19
  • Accepted : 2020.09.28
  • Published : 2021.04.25
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Abstract

In this paper, the mechanical performance of cracked surface-coated Zircaloy cladding, which has different coating materials, coating thicknesses and initial crack lengths, has been investigated. By analyzing the stress field near the crack tip, the safety zone range of initial crack length has been decided. In order to determine whether the crack can propagate along the radial (r) or axial (z) directions, the energy release rate has been calculated. By comparing the energy release rate with fracture toughness of materials, we can divide the initial crack lengths into three zones: safety zone, discussion zone and danger zone. The results show that Cr is suitable coating material for the cladding with a thin coating while Fe-Cr-Al have a better fracture mechanical performance in the cladding with thick coating. The Si-coated and SiC-coated claddings are suitable for reactors with low power fuel elements. Conclusions in this paper can provide reference and guidance for the cladding design of nuclear fuel elements.

Keywords

Acknowledgement

This work was supported by the National Natural Science Foundation of China [11232015, 11572355].

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