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 …
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 …
distributions evolve due to factors such as fission, nuclear transmutation, and elemental …
A Framework to Assess Advanced Reactor Spent Fuel Management Facility Deployment
MI Atz, RA Joseph, EA Hoffman - Nuclear Technology, 2024 - Taylor & Francis
Advanced nuclear reactors offer various operational advantages over existing light water
reactors but could produce types of spent nuclear fuel (SNF) with a wide variety of forms and …
reactors but could produce types of spent nuclear fuel (SNF) with a wide variety of forms and …
Electron probe microanalysis of irradiated FUTURIX-FTA U-Pu-Zr alloy with added minor actinides
Electron microprobe examinations were performed to characterize the chemical features of a
full cross section of irradiated nuclear fuel from the FUTURIX-FTA experiment. This …
full cross section of irradiated nuclear fuel from the FUTURIX-FTA experiment. This …
Microstructure evolution of U–Zr system in a thermal cycling neutron diffraction experiment: extruded U–10Zr (wt.%)
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 …
1073 K with a~ 9 hour hold at 873 K during cooling) was investigated using in situ neutron …
In situ monitoring of microstructure evolution during thermal processing of uranium-zirconium alloys using laser-generated ultrasound
Laser-generated ultrasound was used to monitor microstructure evolution during thermal
processing of as-cast, polycrystalline binary uranium-zirconium metallic fuel alloys with …
processing of as-cast, polycrystalline binary uranium-zirconium metallic fuel alloys with …
High-temperature thermodynamics of uranium from ab initio modeling
We present high-temperature thermodynamic properties for uranium in its γ phase (γ-U) from
first-principles, relativistic, and anharmonic theory. The results are compared to CALPHAD …
first-principles, relativistic, and anharmonic theory. The results are compared to CALPHAD …
Scale modeling of the sodium cooled fast-spectrum advanced burner test reactor
A Shaw, F Bostelmann, D Hartanto, E Walker… - 2023 - osti.gov
This report documents the modeling and simulation of a sodium-cooled fast reactor (SFR) as
part of a US Nuclear Regulatory Commission–sponsored project to assess the modeling …
part of a US Nuclear Regulatory Commission–sponsored project to assess the modeling …
A new model of fission gas bubble growth and mechanism analysis for U-xZr fuels
X Mao, X Chen, X Jian, F Yan, S Ding - Journal of Nuclear Materials, 2025 - Elsevier
U-xZr alloys have a promising application prospect in advanced nuclear fuel elements, and
their macroscale volume growth under the extreme service environments are attracting more …
their macroscale volume growth under the extreme service environments are attracting more …
About the enthalpy of formation of the UZr2 compound
The U-Zr phase diagram has been the subject of many recent studies, particularly for the
development of metallic fuels for future fast reactors. The so-called δ-UZr 2 phase is part of …
development of metallic fuels for future fast reactors. The so-called δ-UZr 2 phase is part of …