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Optimization of Conductive Fins to Minimize UO 2 Fuel Temperature and Radial Temperature Gradient

Author

Listed:
  • Kyle M. Paaren

    (Idaho National Laboratory, 2525 Fremont Ave., Idaho Falls, ID 83415, USA)

  • Pavel Medvedev

    (Idaho National Laboratory, 2525 Fremont Ave., Idaho Falls, ID 83415, USA)

  • Robert Mariani

    (Idaho National Laboratory, 2525 Fremont Ave., Idaho Falls, ID 83415, USA)

Abstract

To further the development of low-enriched uranium fuels, precedence has been placed on delivering the same amount of power while lowering the fuel temperature and radial temperature gradient. To address this, modeling efforts have resulted in a novel design featuring conductive fins of varying thermal conductivities and geometries inserted into the fuel matrix. These conductive inserts were not allowed to exceed 6% of the original fuel volume. This constraint was imposed due to other designs displacing 10% of fuel volume. A parametric study was performed that consisted of 2.56 million BISON simulations involving varying fin characteristics (i.e., fin thermal conductivity, number, and geometry) to determine the optimal geometric configuration for a desired amount of fuel volume displaced. The results from this study show that the thickness and length of each fin affect the fuel temperature and temperature gradient more than varying the number and thermal conductivity of the fins. The parametric study resulted in the development of an optimized combination to produce the lowest peak fuel temperature, lowest radial temperature gradient, and highest temperature reduction for the amount of original fuel volume displaced. The simulations presented in this work will eventually be compared with irradiation experiments of similar fuel designs at Idaho National Laboratory’s Advanced Test Reactor.

Suggested Citation

  • Kyle M. Paaren & Pavel Medvedev & Robert Mariani, 2023. "Optimization of Conductive Fins to Minimize UO 2 Fuel Temperature and Radial Temperature Gradient," Energies, MDPI, vol. 16(6), pages 1-16, March.
  • Handle: RePEc:gam:jeners:v:16:y:2023:i:6:p:2785-:d:1099813
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    References listed on IDEAS

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    1. Mohammad Alrwashdeh & Saeed A. Alameri, 2022. "SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis," Energies, MDPI, vol. 15(10), pages 1-17, May.
    2. Lorenzo Malerba & Abderrahim Al Mazouzi & Marjorie Bertolus & Marco Cologna & Pål Efsing & Adrian Jianu & Petri Kinnunen & Karl-Fredrik Nilsson & Madalina Rabung & Mariano Tarantino, 2022. "Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations," Energies, MDPI, vol. 15(5), pages 1-48, March.
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