Publication Code
IAEA-TECDOC-1923
ID
14699
Publication Type
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.
Cover Image
ISBN
978-92-0-115720-1
Publication Original Id
14699
Publication Year
2020
Publication Date
Publication Issue Date
Publication Series Info
1923
Publication Series Number
1923
Price
18.00
Number of Pages
144
Number of Figures
56
Publication Medium
Print (Paper)
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
Publication File
Publication File Type
application/pdf
Publication File Size
4641
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