Thermal expansion of UO2+x nuclear fuel rods from a model coupling heat transfer and oxygen diffusion

Journal Article · Tue Jan 01 00:00:00 EST 2008 · Journal of Nuclear Materials

OSTI ID:960472

Mihaila, Bogden ^[1]; Zubelewicz, Aleksander ^[1]; Stan, Marius ^[1]; Ramirez, Juan ^[2]

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1. Los Alamos National Laboratory
2. EXPONENT, INC.

We study the thermal expansion of UO{sub 2+x} nuclear fuel rod in the context of a model coupling heat transfer and oxygen diffusion discussed previously by J.C. Ramirez, M. Stan and P. Cristea [J. Nucl. Mat. 359 (2006) 174]. We report results of simulations performed for steady-state and time-dependent regimes in one-dimensional configurations. A variety of initial- and boundary-value scenarios are considered. We use material properties obtained from previously published correlations or from analysis of previously published data. All simulations were performed using the commercial code COMSOL Multiphysics{sup TM} and are readily extendable to include multidimensional effects.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC52-06NA25396
• OSTI ID: 960472
• Report Number(s): LA-UR-08-04952; LA-UR-08-4952; JNUMAM; TRN: US1002048
• Journal Information: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials; ISSN 0022-3115
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
COUPLING
DIFFUSION
HEAT TRANSFER
NUCLEAR FUELS
OXYGEN
FUEL RODS
THERMAL EXPANSION
URANIUM DIOXIDE