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

IAEA TECDOC No. 1923
English IAEA-TECDOC-1923 978-92-0-115720-1
144 56 18.00 2020

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Description

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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Keywords

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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