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Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches

  • Bahareh Roostaii ORCID logo EMAIL logo
Published/Copyright: April 14, 2023
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Kerntechnik
From the journal Kerntechnik Volume 88 Issue 3

Abstract

A correlation for the volume porosity of irradiated UO2 fuel as a sum of the individual contributions of the pore and swelling porosity in terms of the local density and fractional matrix swelling is developed. By using the existing low temperature low burnup model of swelling, evolution of the matrix swelling and porosity terms are calculated for UO2 fuel in the low burnup but in the high burnup two various models are applied, the one with considering grain recrystallization and another without it but with the method of Xe depletion measurement. The purpose of the paper is comparison of fuel swelling behavior between two models at high burnups. The bulk swelling and porosity evolution in both methods are also validated by experimental data. Finally, one conclusion from this comparison is obtained, as the method which considering grain recrystallization has more rational behavior in the fuel swelling and porosity.

Keywords: high burnup structure; matrix swelling; porosity; Xe depletion
Corresponding author: Bahareh Roostaii, Nuclear Science and Technology Research Institute, P. O. Box 11365-3486, Tehran, I. R. Iran, E-mail:

  1. Author contributions: The author has accepted responsibility for the entire content of this submitted manuscript and approved submission.

  2. Research funding: None declared.

  3. Conflict of interest statement: The author declares no conflicts of interest regarding this article.

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Received: 2022-12-10
Published Online: 2023-04-14
Published in Print: 2023-06-27

© 2023 Walter de Gruyter GmbH, Berlin/Boston

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https://doi.org/10.1515/kern-2022-0121
Keywords for this article
high burnup structure; matrix swelling; porosity; Xe depletion

Articles in the same Issue

  1. Frontmatter
  2. Scaling effect on cesium diffusion in compacted MX-80 bentonite for buffer materials in HLW repository
  3. Enhanced heat transfer in corrugated plate fin heat sink
  4. Discussion of options to increase the control drum worth in fast reactor
  5. New semi-empirical systematic of (p,n) reaction cross section at 7.5 MeV
  6. Computational analysis of nuclear desalination system under various configurations
  7. Performance analysis of nuclear powered desalination unit based on MED-TVC: a case study for Saudi Arabia
  8. Analysis of 4-inch cold leg top-slot break LOCA in ATLAS experimental facility using MARS-KS
  9. Evaluating the performance of Indonesia’s nuclear energy program using INPRO methodology
  10. Thermal hydraulic analysis of VVER spent fuels stored in vault dry system under different operating and design conditions
  11. Comparative analysis of swelling and porosity evolution in UO2 fuel via two approaches
  12. Euler–Maruyama algorithm in estimating UGV path and location in nuclear emergency and security applications
  13. Modeling and simulation of deposited energy gain via irradiation of heavy ion beams on the fusion reactor contains spherical fuel capsules with foam
  14. Calendar of events
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