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Journal of Alloys and Compounds, ISSN 0925-8388, 10/2015, Volume 645, pp. 158 - 163
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 05/2016, Volume 473, pp. 223 - 228
Journal Article
Journal of Alloys and Compounds, ISSN 0925-8388, 09/2012, Volume 534, pp. 101 - 109
► U-Mo alloys prepared by splat cooling. ► A small amount of γ-phase was preserved in pure splat-cooled uranium specimen. ► Crystal structure characterized by... 
γ-Uphase | U-Mo alloys | Superconductivity | ELECTRICAL-RESISTIVITY | ALPHA-URANIUM | BEHAVIOR | MATERIALS SCIENCE, MULTIDISCIPLINARY | METALLURGY & METALLURGICAL ENGINEERING | gamma-Uphase | CHEMISTRY, PHYSICAL | Scanning electron microscopy | Cooling | Uranium | Electrical resistivity | Alloys | Molybdenum base alloys | Electron back scatter diffraction
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 05/2016, Volume 473, pp. 206 - 217
Journal Article
Journal of Alloys and Compounds, ISSN 0925-8388, 06/2019, Volume 790, pp. 809 - 813
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 10/2015, Volume 465, pp. 153 - 160
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 06/2019, Volume 519, pp. 287 - 291
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 08/2019, Volume 521, pp. 167 - 244
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 09/2015, Volume 464, Issue C, pp. 331 - 341
•Thermal properties of irradiated U–Mo alloy monolithic fuel samples were measured.•Density, thermal diffusivity, and thermal conductivity are influenced by... 
HEAT | FUEL PLATE | TEMPERATURE | NUCLEAR SCIENCE & TECHNOLOGY | BEHAVIOR | MATERIALS SCIENCE, MULTIDISCIPLINARY | MINING & MINERAL PROCESSING | Thermal properties | Analysis | Alloys | Electric properties | Aluminum base alloys | Irradiation | Thermal conductivity | Density | Heat transfer | Fission | Uranium-Molybdenum | irradiated | thermal properties | nuclear fuel
Journal Article
Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, ISSN 1073-5623, 06/2017, Volume 48, Issue 6, pp. 2819 - 2833
Diffusion couple formed between U-9 wt pct Mo and Zr-1 wt pct Nb alloys, proposed as fuel and clad materials, respectively, in nuclear research reactors, was... 
AL A356 ALLOY | MO/AL DISPERSION FUEL | MATERIALS SCIENCE, MULTIDISCIPLINARY | METALLURGY & METALLURGICAL ENGINEERING | 550 DEGREES-C | IRRADIATION BEHAVIOR | DIFFUSION BARRIER | GROWTH-KINETICS | WT.PERCENT-MO | U-MO | INTERACTION LAYER | MOLYBDENUM ALLOY | Annealing | Zirconium | Interdiffusion | Uranium base alloys | Cladding | Microstructure | Molybdenum | Niobium | Zirconium base alloys
Journal Article
AIP Conference Proceedings, ISSN 0094-243X, 09/2018, Volume 2015, Issue 1
Solubility of lanthanum and uranium was determined in gallium–aluminum and gallium–indium eutectic based pseudo-quaternary U–La–Ga–In and U–La–Ga–Al alloys at... 
Activity coefficients | Gallium base alloys | Uranium | Aluminum | Solubility | Eutectic alloys | Lanthanum | Sedimentation
Journal Article