Simulations of heat and oxygen diffusion in UO2 nuclear fuel rods

Journal of Nuclear Materials

Volumn 359, Issue 3, 2006, Pages 174-184

  Ramirez, J C ^a   Stan, M ^a   Cristea, P ^a  

^a LOS ALAMOS NATIONAL LABORATORY   (United States)

Author keywords

D0300; F0700; M0200; U0200

Indexed keywords

CORRELATION METHODS; DIFFUSION; FINITE ELEMENT METHOD; OXYGEN; THERMAL CONDUCTIVITY; URANIUM COMPOUNDS;

HEAT GENERATION RATE INTENSITY; NUCLEAR FUEL RODS; OXYGEN ATOMS; TRANSIENT REGIME;

NUCLEAR FUELS;

EID: 33751208064     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2006.08.018     Document Type: Article

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