Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Prediction of ballooning and burst for nuclear fuel cladding with anisotropic creep modeling during Loss of Coolant Accident (LOCA)

  • Kim, Jinsu (Department of Mechanical Engineering, Korea Advanced Institute of Science and Technology) ;
  • Yoon, Jeong Whan (Department of Mechanical Engineering, Korea Advanced Institute of Science and Technology) ;
  • Kim, Hyochan (ATF Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Lee, Sung-Uk (ATF Technology Development Division, Korea Atomic Energy Research Institute)
  • Received : 2021.03.04
  • Accepted : 2021.04.15
  • Published : 2021.10.25
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Abstract

In this study, a multi-physics modeling method was developed to analyze a nuclear fuel rod's thermo-mechanical behavior especially for high temperature anisotropic creep deformation during ballooning and burst occurring in Loss of Coolant Accident (LOCA). Based on transient heat transfer and nonlinear mechanical analysis, the present work newly incorporated the nuclear fuel rod's special characteristics which include gap heat transfer, temperature and burnup dependent material properties, and especially for high temperature creep with material anisotropy. The proposed method was tested through various benchmark analyses and showed good agreements with analytical solutions. From the validation study with a cladding burst experiment which postulates the LOCA scenario, it was shown that the present development could predict the ballooning and burst behaviors accurately and showed the capability to predict anisotropic creep behavior during the LOCA. Moreover, in order to verify the anisotropic creep methodology proposed in this study, the comparison between modeling and experiment was made with isotropic material assumption. It was found that the present methodology with anisotropic creep could predict ballooning and burst more accurately and showed more realistic behavior of the cladding.

Keywords

Acknowledgement

This work has been carried out under the Nuclear R&D Program supported by the Ministry of Science and ICT (NRF-2017M2A8A4015024).

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