Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2

Terricabras, Adrien Jose Emile; Drewry, Sean Michael; Campbell, Keri; Judge, Elizabeth J.; Byler, Darrin David; Teti, Emily S.; van Veelen, Arjen; Widgeon Paisner, Scarlett; White, Joshua Taylor

doi:10.1016/j.jnucmat.2024.155022

Title: Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO₂

Journal Article · 16 March 2024 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2024.155022 · OSTI ID:2329260

^[1];

^[2];

^[1]; Judge, Elizabeth J. ^[1]; Byler, Darrin David ^[1];

^[1];

^[1]; White, Joshua Taylor ^[1]

Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Univ. of Tennessee, Knoxville, TN (United States)

Chromium-doped UO₂ fuel has received significant interest due to the ability for chromium to produce pellets with large average grain size (>30 μm), which has shown to increase fission gas retention during operation. Sintering of chromium-doped UO₂ pellets was pursued with oxygen potential and sintering atmosphere controlled to tailor the final microstructure of the material. Chromium additions in this study ranged from 750 to 7800 ppm. Cr concentrations were studied pre and post sintering using Inductively Coupled Plasma Optical Emission Spectroscopy (ICP-OES). Effects of chromium content on lattice parameter and microstructure were examined with X-ray diffraction (XRD) and scanning electron microscopy (SEM). Contraction of the UO₂ lattice parameter was observed, as well as enlargement of grain size with increasing chromium content up to 4900 ppm Cr₂O₃. In addition, SEM indicated Cr incorporation within the matrix and the formation of chromium oxide precipitates throughout the microstructure at high Cr concentrations. Evaluation of thermophysical properties of Cr-doped UO₂ pellets were conducted up to 1200 °C to illustrate their evolution with increased dopant concentration and microstructural changes. The results show that grain size is maximized at 52 μm with Cr₂O₃ concentration equal to 4900 ppm; however, grain size decreases at higher Cr₂O₃ concentrations. No significant changes were observed in specific heat capacity, linear thermal expansion, and coefficient of thermal expansion compared to undoped UO₂. The thermal conductivity also decreased through the incorporation of Cr₂O₃ dopants above 750 ppm and is shown to be ~15 % lower than reported UO₂ values.

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Research Organization:: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: 89233218CNA000001

OSTI ID:: 2329260

Alternate ID(s):: OSTI ID: 2325508

Report Number(s):: LA-UR--23-34124; {"","Journal ID: ISSN 0022-3115"}

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 594; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Title: Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2

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Title: Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO₂