Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Study of the mechanical properties and effects of particles for oxide dispersion strengthened Zircaloy-4 via a 3D representative volume element model

  • Kim, Dong-Hyun (Advanced 3D Printing Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Hong, Jong-Dae (Advanced 3D Printing Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Hyochan (Advanced 3D Printing Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Jaeyong (Advanced 3D Printing Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Hak-Sung (Department of Mechanical Engineering, Hanyang University)
  • Received : 2021.06.28
  • Accepted : 2021.10.31
  • Published : 2022.05.25
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Abstract

As an accident tolerant fuel (ATF) concept, oxide dispersion strengthened Zircaloy-4 (ODS Zry-4) cladding has been developed to enhance the mechanical properties of cladding using laser processing technology. In this study, a simulation technique was established to investigate the mechanical properties and effects of Y2O3 particles for the ODS Zry-4. A 3D representative volume element (RVE) model was developed considering the parameters of the size, shape, distribution and volume fraction (VF) of the Y2O3 particles. From the 3D RVE model, the Young's modulus, coefficient of thermal expansion (CTE) and creep strain rate of the ODS Zry-4 were effectively calculated. It was observed that the VF of Y2O3 particles had a significant effect on the aforementioned mechanical properties. In addition, the predicted properties of ODS Zry-4 were applied to a simulation model to investigate cladding deformation under a transient condition. The ODS Zry-4 cladding showed better performance, such as a delay in large deformation compared to Zry-4 cladding, which was also found experimentally. Accordingly, it is expected that the simulation approach developed here can be efficiently employed to predict more properties and to provide useful information with which to improve ODS Zry-4.

Keywords

Acknowledgement

This work has been carried out supported by the Korea Foundation of Nuclear Safety R&D Program (2101050-0121-CG100).

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