Dissolution of UO2 in molten Zircaloy-4 part 3: Solubility from 2000 to 2500°C

Journal of Nuclear Materials

Volumn 232, Issue 1, 1996, Pages 1-12

  Hayward, P J ^a   George, I M ^a  

^a ATOMIC ENERGY OF CANADA LIMITED   (Canada)

Author keywords

[No Author keywords available]

Indexed keywords

CALCULATIONS; DISSOLUTION; FISSION REACTIONS; LIQUID METALS; NUCLEAR FUEL CLADDING; NUCLEAR FUELS; REGRESSION ANALYSIS; SATURATION (MATERIALS COMPOSITION); SOLUBILITY; TEMPERATURE; VOLUME FRACTION; ZIRCONIUM ALLOYS;

FUEL CLADDING MASS RATIO; FUEL DAMAGE ACCIDENT; UNIRRADIATED URANIUM DIOXIDE; URANIUM SATURATED MELTS; ZIRCALOY;

URANIUM DIOXIDE;

EID: 0030235535     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/0022-3115(96)00200-0     Document Type: Article

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