A critical review of the microstructure of U–Mo fuels

T Ajantiwalay, C Smith, DD Keiser… - Journal of Nuclear …, 2020 - Elsevier
The microstructure of fuels evolves with irradiation and extensive microstructural
characterization has been performed both on as-fabricated and irradiated U–Mo fuels for …

[HTML][HTML] Image-driven discriminative and generative machine learning algorithms for establishing microstructure–processing relationships

W Ma, EJ Kautz, A Baskaran, A Chowdhury… - Journal of Applied …, 2020 - pubs.aip.org
We investigate the methods of microstructure representation for the purpose of predicting
processing condition from microstructure image data. A binary alloy (uranium–molybdenum) …

The effect of homogenization heat treatment on the texture evolution in U-10Mo alloy

BJ Schuessler, DP Field, NR Overman… - … Materials Transactions A, 2021 - Springer
Uranium alloyed with 10 wt pct Mo (U-10Mo) undergoes discontinuous precipitation (DP)
when subjected to sub-eutectoid heat treatment. It is hypothesized that the crystallographic …

XRD and SEM/EDS characterization of two quaternary fuel alloys (U-2.5 Mo-2.5 Ti-5.0 Zr and U-1.5 Mo-1.5 Ti-7.0 Zr in wt.%) for fast reactors

W Zhuo, Y Xie, MT Benson, J Ge, RD Mariani… - Materials …, 2020 - Elsevier
The current study focuses on characterization of two potential fuel alloys for sodium-cooled
fast reactors: U-2.5 Mo-2.5 Ti-5.0 Zr (U-MT5Z) and U-1.5 Mo-1.5 Ti-7.0 Zr (U-MT7Z) in wt …

Preparation of γ-uranium-molybdenum alloys by electrochemical reduction of solid oxides in LiCl molten salt

YK Zhong, K Liu, YL Liu, YX Lu, TQ Yin… - Journal of The …, 2019 - iopscience.iop.org
Abstract Uranium-molybdenum (U-Mo) alloys especially the γ-U-Mo phase, with excellent
irradiation performance at high temperatures, have been extensively studied as low …

Recrystallization kinetics of cold-rolled U-10 wt% Mo

WE Frazier, S Hu, N Overman, R Prabhakaran… - Journal of Nuclear …, 2019 - Elsevier
Samples of U-10 wt% Mo (Usingle bond Mo) alloy were thermomechanically processed and
annealed at 600° C and 700° C for periods lasting up to 8 h. Annealed microstructures were …

[HTML][HTML] Minimizing thickness variation in monolithic U-10Mo fuel foil and Zr interlayer during hot rolling: A microstructure-based finite element method analysis

L Li, A Fortier, D Ramirez-Tamayo, VV Joshi… - Materials Today …, 2022 - Elsevier
Low-enriched uranium alloyed with 10 wt.% molybdenum (U-10Mo) has been identified as a
promising alternative to highly enriched uranium fuel for the United States' high performance …

Calculation of grain boundary diffusion coefficients in γU-Mo using atomistic simulations

ATMJ Hasan, B Beeler - Journal of Nuclear Materials, 2024 - Elsevier
The γU-Mo alloy has been selected for the conversion of US High-Performance Research
Reactor (HPRR) fuel from highly enriched uranium to low enriched uranium as a part of the …

An electron backscatter diffraction analysis of grain boundary initiated discontinuous precipitation in U–10Mo

NR Overman, S Jana, DP Field, C Lavender… - Journal of Nuclear …, 2020 - Elsevier
The effect of varied thermomechanical processing on discontinuous precipitation (DP) in U–
10Mo was investigated, with specific emphasis on understanding the role of grain boundary …

Influence of processing on secondary phase formation and microstructural evolution at U-10Mo alloy and Zr interlayer interfaces

EJ Kautz, M Song, S Riechers, A Koziol… - Journal of Alloys and …, 2023 - Elsevier
Thermo-mechanical processing of uranium-10 wt% molybdenum (U-10Mo) alloy fuel plates
with a zirconium (Zr) interlayer leads to microstructure changes at fuel/interlayer interfaces …