Recent trends in metallic fast reactor fuels research

A Aitkaliyeva - Journal of Nuclear Materials, 2022 - Elsevier
Metallic nuclear fuels have been extensively investigated for more than 60 years. Early
studies noted that metallic fuels exhibit characteristic irradiation behaviors that set them …

Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing

KA Terrani, NA Capps, MJ Kerr, CA Back… - Journal of Nuclear …, 2020 - Elsevier
An approach to transform and accelerate nuclear fuel development and qualification is
outlined. The approach exploits advanced modeling and simulation at the outset to inform …

Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm

GL Beausoleil, C Petrie, W Williams… - Nuclear …, 2021 - Taylor & Francis
With the increasing interest in sodium fast reactor technology, as seen by applications to the
US Nuclear Regulatory Commission for the OKLO Aurora plant, fuel testing for the …

Transmission electron microscopy study of a high burnup U-10Zr metallic fuel

D Salvato, X Liu, DJ Murray, KM Paaren, F Xu… - Journal of Nuclear …, 2022 - Elsevier
To support the development of U-10 wt.% Zr (U-10Zr) metallic fuel for Generation IV sodium-
cooled fast reactors, we analyzed a Na-bonded solid U-10Zr fuel cross-section that was …

Irradiation softening in a uranium containing NbTiZrU high entropy alloy induced by Xe ion implantation

T Fu, Y Zhu, H Pan, J Shi, T Yi, D Xie, Z Shen… - Materials Today …, 2025 - Elsevier
In this work, a novel uranium-containing single-phase bcc NbZr 0.6 Ti 0.4 U x (x= 0.4, 1, 2)
high entropy alloy (HEA, named as U20, U50 and U100) film was designed and prepared …

Microstructure evolution of U–Zr system in a thermal cycling neutron diffraction experiment: extruded U–10Zr (wt.%)

Y Xie, SC Vogel, JM Harp, MT Benson… - Journal of Nuclear …, 2021 - Elsevier
Microstructure evolution of 1073 K extruded U–10Zr (wt.%) fuel during thermal cycling (303–
1073 K with a~ 9 hour hold at 873 K during cooling) was investigated using in situ neutron …

Determining the effects of U/Pu ratio on subsolidus phase transitions in U-Pu-Zr metallic fuel alloys

S Middlemas, DE Janney, C Adkins… - Journal of Nuclear …, 2024 - Elsevier
Ternary alloys consisting primarily of uranium, plutonium, and zirconium (U-Pu-Zr) are
among the leading candidate fuel systems considered for fast spectrum nuclear reactors …

Development of U-Zr-Xe ternary interatomic potentials appropriate for simulation of defect and Xe behaviors in U-Zr system

P Jiang, R Qiu, J Cao, X Liao, Y Chen, Z Liu… - Journal of Nuclear …, 2024 - Elsevier
U-10Zr metallic fuel (alloys of U with 10 wt% Zr) is considered as a potential candidate for
fast reactors due to its excellent performance. However, the fission gas swelling has a …

Phase evolution of U-Zr system in a thermal cycling neutron diffraction experiment: as-cast U-35Zr and U-50Zr

Y Xie, SC Vogel, MT Benson, JM Harp - Journal of Nuclear Materials, 2022 - Elsevier
Phase evolution of as-cast U-35 wt% Zr and U-50 wt% Zr alloys during thermal cycling (303–
1073 K) was investigated using in-situ neutron diffraction. Analysis was performed using …

TEM-based phase characterization of U–19Pu–10Zr irradiated in ATR

T Rahn, BD Miller, L Capriotti, A Aitkaliyeva - MRS Bulletin, 2023 - Springer
This article reports the results of the microstructural examination of the irradiated U–19Pu–
10Zr fuel. New insights gained using selective area electron diffraction analysis in a …