Uranium-zirconium hydride fuel properties

Nuclear Engineering and Design

Volumn 239, Issue 8, 2009, Pages 1406-1424

  Olander, D ^a   Greenspan, Ehud ^a   Garkisch, Hans D ^b   Petrovic, Bojan ^c  

^a Etcheverry Hall MCI 730   (United States)

^b WESTINGHOUSE ELECTRIC COMPANY   (United States)

^c GEORGIA INSTITUTE OF TECHNOLOGY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

AUXILIARY POWER; DATA BASE; DESIGN CONSTRAINTS; DESIGN LIMITS; FABRICATION METHOD; FISSION GAS; FUEL PELLETS; FUEL RODS; FUEL-CLADDING GAP; GAP THICKNESS; HEAT OF TRANSPORT; HIGH THERMAL CONDUCTIVITY; HYDRIDE FUEL; INITIAL GAP; MAXIMUM FUEL TEMPERATURES; MECHANICAL INTERACTIONS; METAL BONDS; METAL HYDRIDES; OXIDE FUELS; RARE EARTH OXIDE; SWELLING RATES; TEMPERATURE DROPS; TEMPERATURE GRADIENT; TEMPERATURE LIMITATION; TRIGA RESEARCH REACTOR; URANIUM PARTICLES; VOID FORMATION; ZIRCONIUM HYDRIDE;

FISSION PRODUCTS; HELIUM; HYDRIDES; HYDROGEN; HYDROGEN FUELS; LIQUID METALS; NUCLEAR FUELS; OXYGEN; PELLETIZING; RARE EARTH ELEMENTS; TENSILE STRESS; THERMAL CONDUCTIVITY; THERMAL EXPANSION; THERMAL GRADIENTS; THERMOANALYSIS; TRANSURANIUM ELEMENTS; URANIUM; ZIRCONIUM; ZIRCONIUM ALLOYS; ZIRCONIUM COMPOUNDS;

LEAKAGE (FLUID);

EID: 67349270266     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2009.04.001     Document Type: Article

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