Experimentally known properties of U-10Zr alloys: A critical review

DE Janney, SL Hayes - Nuclear Technology, 2018 - Taylor & Francis
Abstract More than 14 000 U-10Zr fuel rods (alloys of U with 10 wt% Zr) were irradiated in
the Experimental Breeder Reactor II and Fast Flux Test Facility, with some irradiated to …

A critical review of the experimentally known properties of U-Pu-Zr alloys. Part 1: phases and phase diagrams

DE Janney, SL Hayes, CA Adkins - Nuclear Technology, 2019 - Taylor & Francis
Abstract The U-Pu-Zr metallic fuels contain multiple phases whose properties and
distributions evolve due to factors such as fission, nuclear transmutation, and elemental …

Preliminary thermo-mechanical couplingperformance analysis of a three-lobe petal-shaped fuel rod

B He, S Qin, A Han, W Zhang, L Du, X Meng… - … Engineering and Design, 2025 - Elsevier
In this paper, an analytical model of thermal–mechanical coupling performance of three-lobe
and four-lobe petal-shaped fuel rods (PSFRs) irradiation is established based on the finite …

Thermal-Mechanical performance analysis of a petal-shaped fuel rod under RIA condition

B He, Y Hou, W Zhang, X Meng, W Cai - Nuclear Engineering and Design, 2024 - Elsevier
This paper establishes the performance analysis model of a petal-shaped fuel rod (PSFR)
under Reactivity Initiated Accident (RIA) condition based on thermal elastic–plastic theory …

Ab initio molecular dynamics investigation of γ-(U, Zr) structural and thermal properties as a function of temperature and composition

A Aly, B Beeler, M Avramova - Journal of Nuclear Materials, 2022 - Elsevier
Uranium in its metallic form is considered as a fuel for sodium fast reactors due to its higher
thermal conductivity and high fissile material density relative to UO 2 fuel. The metal is …

Temperature and composition dependent thermal conductivity model for U-Zr alloys

W Chen, XM Bai - Journal of Nuclear Materials, 2018 - Elsevier
Abstract Uranium-zirconium (U-Zr) based metallic fuels are promising fuel forms for next-
generation fast reactors. The presence of temperature gradient and constituent redistribution …

Atomistic calculations of the surface energy as a function of composition and temperature in γ U–Zr to inform fuel performance modeling

B Beeler, A Casagranda, L Aagesen, Y Zhang… - Journal of Nuclear …, 2020 - Elsevier
Uranium-zirconium alloy fuels are candidates for advanced sodium cooled fast reactors due
to their high uranium density, high thermal conductivity, inherent safety and ability to …

Postirradiation Examination of FUTURIX-FTA metallic alloy experiments

JM Harp, L Capriotti, HJM Chichester - Journal of Nuclear Materials, 2019 - Elsevier
Two different metallic nuclear fuel alloys intended for transmutation applications in fast
neutron spectrum nuclear reactors have been irradiated, and their performance has been …

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 …

Solidification-induced nonuniformity in U–Zr–RE metallic nuclear fuel rods

SU Mun, G Oh, JH Kim, SG Park, BM Weon - Scientific Reports, 2024 - nature.com
Metallic fuel is being developed for the next generation of sodium-cooled fast reactors due to
its safety and fuel cycle economics through spent fuel reprocessing technology. After spent …