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Mechanical behavior of a fuel pin under irradiation: fuel cladding interaction at high power rate

Calza-Bini, A.; Cosoli, G.; Filacchioni, G.; Lanchi, M.; Nobili, A.; Pesce, E.; Rocca, U.; Rotoloni, P.L.1975

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AbstractAbstract

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Original Title

UO₂-PuO₂

Primary Subject

GENERAL STUDIES OF NUCLEAR REACTORS (E2300)

Source

European nuclear conference; Paris, France; 21 Apr 1975; Published in summary form only.

Record Type

Journal Article

Literature Type

Conference

Journal

Transactions of the American Nuclear Society; v. 20 p. 229-231

Country of publication

Descriptors (DEI)

DEFORMATION, FUEL CANS, FUEL PINS, FUEL-CLADDING INTERACTIONS, IRRADIATION, MATHEMATICAL MODELS, PLUTONIUM DIOXIDE, POWER DENSITY, STRAINS, URANIUM DIOXIDE, ZIRCALOY 2

Descriptors (DEC)

ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, CHROMIUM ADDITIONS, FUEL ELEMENTS, IRON ADDITIONS, OXIDES, OXYGEN COMPOUNDS, PLUTONIUM COMPOUNDS, PLUTONIUM OXIDES, REACTOR COMPONENTS, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS, URANIUM OXIDES, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS

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