Improvement of fuel performance code COSMOS with recent in-pile data for MOX and UO2 fuels

Nuclear Technology

Volumn 157, Issue 1, 2007, Pages 53-64

  Lee, Byung Ho ^a   Koo, Yang Hyun ^a   Oh, Je Yong ^a   Cheon, Jin Sik ^a   Sohn, Dong Seong ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

COSMOS; MOX fuel; Performance code

Indexed keywords

CREEP; IRRADIATION; MIXED OXIDE FUELS; NUCLEAR FUEL CLADDING; NUCLEAR REACTORS; PERFORMANCE; THERMAL CONDUCTIVITY; URANIUM ALLOYS;

FISSION GAS RELEASE; FUEL PERFORMANCE; THERMAL BEHAVIOR;

NUCLEAR FUEL ELEMENTS;

EID: 33846396413     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT07-A3801     Document Type: Article

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