| About this Abstract |
| Meeting |
2016 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Fuels for the Current and Advanced Nuclear Reactors V
|
| Presentation Title |
Thermal Conductivity of High Plutonium Content MOX Fuels |
| Author(s) |
Dragos Staicu, Somers Joe, Wiss Thierry, Konings Rudy, J.M. |
| On-Site Speaker (Planned) |
Dragos Staicu |
| Abstract Scope |
The thermophysical properties of high plutonium content MOX fuels were investigated, with samples synthesised by mechanical blending of powders and sol gel routes.
The thermal diffusivity and density were measured for (U,Pu)O2 samples with Pu contents of 40 and 45%.
The thermal conductivity of (U0.6Pu0.4)O2 and (U0.55Pu0.45)O2 was calculated using literature data for the specific heat and thermal dilatation coefficients. Considering the uncertainties, the thermal conductivities of the samples with similar Pu contents are equal, and no significant difference is observed between the Pu contents of 40% (mechanically milled) and 45% (sol-gel).
The results are compared to the recommendation of Philipponneau for FBR MOX with 15 to 30 % Pu and the investigated samples clearly have a higher thermal conductivity, illustrating the fact that the validity range of this particular correlation for FBR MOX cannot be extended to these high Pu contents. A recommendation for the thermal conductivity is proposed. |
| Proceedings Inclusion? |
Planned: A print-only volume |