Interdiffusion in uranium-zirconium solid solutions
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference12 articles.
1. Fuel constituent redistribution during the early stages of U-Pu-Zr irradiation
2. Demixing of U-Zr alloys under a thermal gradient
3. Constituent Migration Model for U-Pu-Zr Metallic Fast Reactor Fuel
4. Temperature gradient driven constituent redistribution in UZr alloys
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1. Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction;Journal of Nuclear Materials;2023-06
2. Thermodynamic and diffusion databases for uranium-based alloys and their applications in materials design;Journal of Nuclear Materials;2023-04
3. An ab-initio based semi-empirical thermal conductivity model for multiphase uranium-zirconium alloys;Journal of Nuclear Materials;2021-09
4. Microstructure Evolution of U–Zr System in A Thermal Cycling Neutron Diffraction Experiment: Extruded U–10Zr (wt. %);Journal of Nuclear Materials;2021-02
5. Laser induced breakdown spectroscopy application to reaction-diffusion studies in nuclear materials;Spectrochimica Acta Part B: Atomic Spectroscopy;2020-04
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