Fabrication of UO2–Mo composite fuel pellets with enhanced thermal conductivity by using wet mixing

Uranium dioxide (UO₂) is the standard nuclear fuel for light water reactors (LWRs) due to its operational experience, irradiation stability, and ease of manufacture. However, its low thermal conductivity results in a high temperature gradient across the pellet in-service, leading to thermal stresses, deformation, and cracking. This study explores the addition of a high thermal conductivity molybdenum phase as a nano-powder, which is trialled alongside pre-sintered UO 2 granules to improve the thermal conductivity of the resulting pellet. UO 2 - 10 wt. % Mo composite pellets were fabricated by dispersing UO₂ granules and nano-Mo powder in ethanol during mixing, followed by ethanol evaporation and subsequent Spark Plasma Sintering (SPS) at 1473 K with a 5-minute hold. Pellet microstructures were characterized using scanning electron microscopy (SEM) and X-ray diffraction (XRD). Pellet thermal conductivity was measured by the laser flash method. Significant improvements in thermal conductivity were observed in the as-manufactured pellets with increases of up to 75% at 1073K for the pellets produced from nano-Mo and pre-sintered UO 2 granules compared to a pure UO₂ pellet. These results highlight the effectiveness of nano-Mo addition and the pre-sintering of UO 2 granules in enhancing the thermal performance of UO₂-based nuclear fuel composites.

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Publication Details

Journal
Journal of Nuclear Materials
Published
2026-01-06
DOI
https://doi.org/10.1016/j.jnucmat.2026.156440
Primary Topic
Nuclear Materials and Properties
Type
article
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article

Fabrication of UO2–Mo composite fuel pellets with enhanced thermal conductivity by using wet mixing

Joel Turner, T. Abram, Hywel Ragnauth, Fihan Alharbi
Journal of Nuclear Materials
Nuclear Materials and Properties
article

Fabrication of UO2–Mo composite fuel pellets with enhanced thermal conductivity by using wet mixing

Joel Turner, T. Abram, Hywel Ragnauth, Fihan Alharbi
article en

Abstract

Uranium dioxide (UO₂) is the standard nuclear fuel for light water reactors (LWRs) due to its operational experience, irradiation stability, and ease of manufacture. However, its low thermal conductivity results in a high temperature gradient across the pellet in-service, leading to thermal stresses, deformation, and cracking. This study explores the addition of a high thermal conductivity molybdenum phase as a nano-powder, which is trialled alongside pre-sintered UO 2 granules to improve the thermal conductivity of the resulting pellet. UO 2 - 10 wt. % Mo composite pellets were fabricated by dispersing UO₂ granules and nano-Mo powder in ethanol during mixing, followed by ethanol evaporation and subsequent Spark Plasma Sintering (SPS) at 1473 K with a 5-minute hold. Pellet microstructures were characterized using scanning electron microscopy (SEM) and X-ray diffraction (XRD). Pellet thermal conductivity was measured by the laser flash method. Significant improvements in thermal conductivity were observed in the as-manufactured pellets with increases of up to 75% at 1073K for the pellets produced from nano-Mo and pre-sintered UO 2 granules compared to a pure UO₂ pellet. These results highlight the effectiveness of nano-Mo addition and the pre-sintering of UO 2 granules in enhancing the thermal performance of UO₂-based nuclear fuel composites.

Journal of Nuclear MaterialsVol. 623
University of Manchester (GB)
Affordable and clean energy
Openalex Percentile: Top 95%
Nuclear Materials and Properties
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