Results of the Irradiation of R6R018 in the Advanced Test Reactor

Robinson, Adam; Wachs, Daniel M.; Medvedev, Pavel; Clark, Curtis; Chang, G. S.; Lillo, M. A.; Jue, Jan‐Fong; Moore, George A.; Wight, Jared

doi:10.2172/986947

Cited by 2 publications

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Thermal conductivity of U–Mo/Al dispersion fuel: effects of particle shape and size, stereography, and heat generation

Cho

Sohn

Kim

2015

Journal of Nuclear Science and Technology

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This paper describes the effects of particle sphericity, interfacial thermal resistance, stereography, and heat generation on the thermal conductivity of U-Mo/Al dispersion fuel. The ABAQUS finite element method (FEM) tool was used to calculate the effective thermal conductivity of U-Mo/Al dispersion fuel by implementing fuel particles. For U-Mo/Al, the particle sphericity effect was insignificant. However, if the effect of the interfacial thermal resistance between the fuel particles and Al matrix was considered, the thermal conductivity of U-Mo/Al was increased as the particle size increases. To examine the effect of stereography, we compared the two-dimensional modeling and three-dimensional modeling. The results showed that the two-dimensional modeling predicted lower than the three-dimensional modeling. We also examined the effect of the presence of heat sources in the fuel particles and found a decrease in thermal conductivity of U-Mo/Al from that of the typical homogeneous heat generation modeling.

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Thermal conductivity of U–Mo/Al dispersion fuel: effects of particle shape and size, stereography, and heat generation

Cho

Sohn

Kim

2015

Journal of Nuclear Science and Technology

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First Results of Scanning Thermal Diffusivity Microscope (STDM) Measurements on Irradiated Monolithic and Dispersion Fuel

Huber¹,

Figg²,

Kennedy³

et al. 2012

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The evolution of thermal conductivity and related changes in thermal diffusivity during irradiation of research-reactor fuel plays a significant role in fuel element performance. To correctly simulate the heat fluxes and temperatures in the fuel meat during normal reactor operation, and also during potential accident scenarios, it is crucial to investigate the change in thermal conductivity and, thus, thermal diffusivity as a function of fission density and U-235 burnup.

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Results of the Irradiation of R6R018 in the Advanced Test Reactor

Cited by 2 publications

References 0 publications

Thermal conductivity of U–Mo/Al dispersion fuel: effects of particle shape and size, stereography, and heat generation

Thermal conductivity of U–Mo/Al dispersion fuel: effects of particle shape and size, stereography, and heat generation

First Results of Scanning Thermal Diffusivity Microscope (STDM) Measurements on Irradiated Monolithic and Dispersion Fuel

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