Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets

UO2 pellets containing molybdenum networks were fabricated when UO2 pellets mixed with 3 or 5wt% MoO3 powder were sintered in the CO2/CO ratio of 19/1 and then annealed in an H2 atmosphere. The thermal diffusivities of UO2 and Mo-precipitated UO2 pellets were measured in the range of 298–1673K by a...

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Veröffentlicht in:Journal of nuclear materials 2006-06, Vol.352 (1-3), p.151-156
Hauptverfasser: Kim, Si-Hyung, Joung, Chang-Young, Kim, Han-Soo, Lee, Young-Woo, Ryu, Ho-Jin, Sohn, Dong-Seong, Kim, Dong-Joo
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container_end_page 156
container_issue 1-3
container_start_page 151
container_title Journal of nuclear materials
container_volume 352
creator Kim, Si-Hyung
Joung, Chang-Young
Kim, Han-Soo
Lee, Young-Woo
Ryu, Ho-Jin
Sohn, Dong-Seong
Kim, Dong-Joo
description UO2 pellets containing molybdenum networks were fabricated when UO2 pellets mixed with 3 or 5wt% MoO3 powder were sintered in the CO2/CO ratio of 19/1 and then annealed in an H2 atmosphere. The thermal diffusivities of UO2 and Mo-precipitated UO2 pellets were measured in the range of 298–1673K by a laser flash method and their thermal conductivities were calculated from the thermal diffusivity, the sample density and the published specific heat capacity data. The temperature dependency of the thermal conductivity up to 1673K in UO2 and Mo-precipitated UO2 was found to be modeled well using the conductivity equation, κ=(A+BT)−1. The thermal conductivity of the Mo-precipitated UO2 was higher than that of the pure UO2.
doi_str_mv 10.1016/j.jnucmat.2006.02.049
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subjects Applied sciences
Energy
Exact sciences and technology
Fuels
Nuclear fuels
Preparation and processing of nuclear fuels
title Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets
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