Analysis of radially resolved thermal conductivity in high burnup mixed oxide fuel and comparison to thermal conductivity correlations implemented in fuel performance codes
Author:
Funder
Idaho National Laboratory
U.S. Department of Energy
Office of Nuclear Energy
Laboratory Directed Research and Development
Publisher
Elsevier BV
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1. Corrigendum to “Analysis of radially resolved thermal conductivity in high burnup mixed oxide fuel and comparison to thermal conductivity correlations implemented in fuel performance codes” [Journal of Nuclear Materials, Volume 596, 1 August 2024, 155090];Journal of Nuclear Materials;2024-11
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