Implications of point defect accumulation on UO2 thermal conductivity and fission gas release under accelerated fuel irradiation

Alshannaq, Mutaz; Owen, Charlie; Ferrigno, Joshua; Minaruzzaman, Md; Abdel-Khalik, Hany S.; Raj, Anant; Pavlov, Tsvetoslav R.; Khafizov, Marat

doi:10.1016/j.jnucmat.2025.156057

Implications of point defect accumulation on UO₂ thermal conductivity and fission gas release under accelerated fuel irradiation

Journal Article · Tue Jul 29 00:00:00 EDT 2025 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2025.156057· OSTI ID:3017247

^[1]; Owen, Charlie ^[2]; Ferrigno, Joshua ^[3]; Minaruzzaman, Md ^[1]; Abdel-Khalik, Hany S. ^[2]; ^[2]; Pavlov, Tsvetoslav R. ^[4]; ^[1]

The Ohio State Univ., Columbus, OH (United States)
Purdue Univ., West Lafayette, IN (United States)
The Ohio State Univ., Columbus, OH (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Evaluation of thermal properties is a crucial factor for nuclear fuel performance. During reactor operation, the accumulation of fission products and irradiation-induced lattice defects are responsible for degradation in thermal conductivity. Consequently, it affects fuel temperature and fission gas release (FGR) among other Multiphysics processes important for economics and safety analysis. We analyze the implications of point defects (PD) accumulation described using a rate theory (RT) Model on lattice thermal conductivity of UO₂. Here, we demonstrate that fission rate-dependent point defect concentrations have the largest impact on in-pile thermal conductivity in the periphery of light water reactor fuels below a temperature threshold governed by the migration barrier of defects. Our analysis provides a mechanistic description of this phenomena which current fuel performance codes treat empirically. The reduction of thermal conductivity in the low -temperature rim region acts as additional thermal resistance and leads to a temperature notably larger than suggested by Lucuta thermal conductivity correlation. These effects are anticipated to have notable impacts when fuels are exposed to accelerated radiation. The impact of such point defect-informed treatment of thermal conductivity on fuel performance is evaluated by a detailed analysis of fission gas behavior and its release. We consider several models capturing different stages of fission gas bubble evolution and fission gas release (FGR). Finally, a new fission rate-dependent correction to the Lucuta correlation is proposed. The results show a significant reduction in thermal conductivity at the fuels’ periphery and an increase in fuel centerline temperature specifically at low burnups. Ultimately a modified LC shows a higher FGR compared to the original LC, while the acceleration process results in a reduction in overall FGR.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)

Grant/Contract Number:: AC07-05ID14517; NE0009269

OSTI ID:: 3017247

Report Number(s):: INL/JOU--24-82622

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 616; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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