TY - GEN
T1 - Three dimensional coupled simulation of plutonium, oxygen and heat diffusion in mixed oxide (U, Pu)O2 fast reactor fuel
AU - Liu, Rong
AU - Zhou, Wenzhong
AU - Yang, Gang
PY - 2014
Y1 - 2014
N2 - Plutonium and oxygen diffusion with the high temperature gradient is one of the important fuel performance concerns in fast reactor (U, Pu)O2 fuel during irradiation, and will affect nuclear fuel materials properties, power distribution and overall performance of the fuel pin. This paper focuses on the plutonium, oxygen and heat diffusion within (U, Pu)O2 fast reactor fuel pellets. In this study, the correlations from the literature are used for thermal conductivity, specific heat, density, plutonium diffusion and oxygen diffusion. Three dimensional burnup dependent oxygen diffusion, plutonium diffusion and heat diffusion models are fully-coupled in steady states and transients to account for the effects on each other. The models are implemented into COMSOL Multiphysics to perform this analysis.
AB - Plutonium and oxygen diffusion with the high temperature gradient is one of the important fuel performance concerns in fast reactor (U, Pu)O2 fuel during irradiation, and will affect nuclear fuel materials properties, power distribution and overall performance of the fuel pin. This paper focuses on the plutonium, oxygen and heat diffusion within (U, Pu)O2 fast reactor fuel pellets. In this study, the correlations from the literature are used for thermal conductivity, specific heat, density, plutonium diffusion and oxygen diffusion. Three dimensional burnup dependent oxygen diffusion, plutonium diffusion and heat diffusion models are fully-coupled in steady states and transients to account for the effects on each other. The models are implemented into COMSOL Multiphysics to perform this analysis.
UR - http://www.scopus.com/inward/record.url?scp=84911951018&partnerID=8YFLogxK
UR - https://www.scopus.com/record/pubmetrics.uri?eid=2-s2.0-84911951018&origin=recordpage
U2 - 10.1115/ICONE22-30641
DO - 10.1115/ICONE22-30641
M3 - RGC 32 - Refereed conference paper (with host publication)
SN - 9780791845899
VL - 1
BT - International Conference on Nuclear Engineering, Proceedings, ICONE
PB - American Society of Mechanical Engineers
T2 - 2014 22nd International Conference on Nuclear Engineering, ICONE 2014
Y2 - 7 July 2014 through 11 July 2014
ER -