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Material Properties of Unirradiated Uranium–Molybdenum (U–Mo) Fuel for Research Reactors


English IAEA-TECDOC-1923 ¦ 978-92-0-115720-1

144 pages ¦ 56 figures ¦ € 18.00 ¦ Date published: 2020

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This publication presents the material properties of all unirradiated Uranium–Molybdenum (U-Mo) fuel constituents that are essential for fuel designers and reactor operators to evaluate the fuel’s performance and safety for research reactors. Many significant advances in the understanding and development of low enriched uranium U–Mo fuels have been made since 2004, stimulated by the need to understand irradiation behavior and early fuel failures during testing. The publication presents a comprehensive overview of mechanical and physical property data from U-Mo fuel research.

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Material, Properties, Material Properties, Unirradiated, U-Mo, Uranium–Molybdenum, Fuel, Research, Reactor, Research Reactor, Development, R&D, Research and Development, Uranium, Uranium Enrichment, Reactor Fuel, Irradiation, Unirradiated Material, Fuel Designer, Reactor Operator, Performance, Safety, Data Sources, Units, Conversions, Temperature Scales, Equilibrium, Phase, Diagram, Melting Temperature, Transformation, Kinetics, Room Temperature, Density, Thermal Expansion, Density Change, Alloy, U-Mo Alloy, Heat Capacity, Thermal Conductivity, Mechanical Properties, Cladding Properties, Matrix Materials, Dispersion, Dispersion Fuel Meats, Burnable Absorbers, DU, Depleted Uranium, LEU, Low Enriched Uranium

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