Effects of ZrN coating and heat treatment on U-Mo dispersion fuel systems under irradiation

Park, Jaewoo; Salvato, Daniele; Robinson, Adam B.; Hanson, William Alexander; Jue, Jan-Fong; Trowbridge, Tammy L.; Giglio, Jeffrey J.

doi:10.1016/j.jnucmat.2025.156412

Effects of ZrN coating and heat treatment on U-Mo dispersion fuel systems under irradiation

Journal Article · Wed Dec 24 00:00:00 EST 2025 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2025.156412· OSTI ID:3020305

^[1]; ^[1]; Robinson, Adam B. ^[1]; ^[1]; Jue, Jan-Fong ^[1]; ^[1]; Giglio, Jeffrey J. ^[1]

Idaho National Laboratory (INL), Idaho Falls, ID (United States)

The stability of U-Mo fuel particles embedded in an Al matrix under irradiation can be enhanced through ZrN coatings and/or heat treatment. Here, the present study investigates the irradiation behavior of fuel plates containing U-Mo fuel particles fabricated under various heat-treatment conditions and ZrN coating thicknesses. Different fission densities were also applied to each fuel plate to evaluate the effects of these variables. Results indicate that higher fission densities lead to more grain recrystallization and high burnup structure (HBS) development in the fuel particles. Heat treatment was found to mitigate the accumulation of fission gas bubbles in fuel particles at low fission densities by coarsening their grains. Fuel particles with ZrN coatings of a 1.2 μm thickness or above exhibited reduced formation of U-Mo/Al interaction layers, suggesting the existence of a critical ZrN coating thickness that minimizes the development of these layers. Fission gas bubbles were predominantly observed at grain boundaries of U-Mo fuel particles irradiated at low fission densities. Subgrain boundaries, which appeared to originate from the original grain boundaries containing fission gas bubbles or HBSs, were also observed, indicating the early stage of HBS propagation in the fuel particles.

View Accepted Manuscript (DOE)

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

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA); USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 3020305

Report Number(s):: INL/JOU--25-87441

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 622; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 - MATERIALS SCIENCE
U-Mo dispersion fuel
U-Mo/Al interaction
ZrN coating
grain recrystallization
high burnup structure

Effects of ZrN coating and heat treatment on U-Mo dispersion fuel systems under irradiation

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