Sintering behavior and thermal conductivity of graphite flakes/uranium dioxide composites
Source abstract
Abstract
Abstract Graphite flakes (GFs) were introduced into UO2 via spark plasma sintering to improve its thermal conductivity (TC). The effect of GFs on the sintering behavior and TC of GFs/UO2 was systematically investigated. GFs/UO2 composites exhibited a highly oriented structure; thus, the radial TC was significantly higher than the axial TC. GFs/UO2 was crack-free below a sintering temperature of 1673 K. At higher temperatures, some cracks were formed owing to the reaction at the interface. Accordingly, the radial TC of GFs/UO2 reached its peak value at 1673 K. The radial TC presented a nearly linear relationship with the GF fraction. The radial TC of GFs/UO2 composites was averagely improved by 340% from 298 to 1273 K with 15 vol.% GFs addition. The radial TC continuously increased with the diameter of the GFs. In contrast, the volume fraction and diameter of the GFs had a relatively inconspicuous effect on the axial TC. This was attributed to the thermal resistance of the interface and deflection of GFs from the radial direction.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Graphite, nuclear technology, radiation studies · Nuclear materials and radiation effects
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (33)
Show source-provided references
1. Hollenbach · 2010
2. Accident tolerant fuels for LWRs: a perspective10.1016/j.jnucmat.2013.12.005 ↗
3. Thermal conductivity of UO2-BeO pellet10.1080/18811248.1996.9731875 ↗
4. High temperature thermal physical performance of BeO/UO2 composites prepared by spark plasma sintering (SPS)10.1016/j.scriptamat.2017.08.031 ↗
5. Manufacture of a UO2-based nuclear fuel with improved thermal conductivity with the addition of BeO
6. Solomon · 2006
7. Enhanced thermal conductivity of uranium dioxide–silicon carbide composites fuel pellets prepared by spark plasma sintering (SPS)10.1016/j.jnucmat.2012.09.015 ↗
8. High temperature thermal physical performance of SiC/UO2 composites up to 1600 °C10.1016/j.ceramint.2018.02.208 ↗
9. Fabrication of UO2-Mo composites fuel with enhanced thermal conductivity from sol-gel feedstock10.1016/j.jnucmat.2019.04.011 ↗
10. Uranium dioxide-molybdenum composites fuel pellets with enhanced thermal conductivity manufactured via spark plasma sintering10.1016/j.jnucmat.2019.05.059 ↗
11. Fabrication of micro-cell UO2-Mo pellet with enhanced thermal conductivity10.1016/j.jnucmat.2015.04.003 ↗
12. SiC whisker strengthened UO2-Mo composites pellets with superior thermal-mechanical properties10.1016/j.ceramint.2019.08.039 ↗
13. Raman spectroscopic investigation of graphitization of diamond during spark plasma sintering of UO2-diamond composites nuclear fuel10.1016/j.jnucmat.2016.03.015 ↗
14. Spark plasma sintering of diamond-reinforced uranium dioxide composites fuel pellets10.1016/j.nucengdes.2015.08.021 ↗
15. Influence of carbon nanotube dispersion in UO2-carbon nanotube ceramic matrix composites utilizing spark plasma sintering10.13182/NT14-7 ↗
16. Thermally-conductive and mechanically-robust graphene nanoplatelet reinforced UO2 composites nuclear fuels10.1038/s41598-018-21034-4 ↗
17. UO2-UN composites with enhanced uranium density and thermal conductivity10.1016/j.jnucmat.2015.06.039 ↗
18. U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels10.1016/j.jnucmat.2020.152147 ↗
19. Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering10.1016/j.jnucmat.2020.152690 ↗
20. Graphite flakes/UO2 fuel pellets with excellent thermal conductivity in radial direction10.1016/j.jnucmat.2020.152639 ↗
21. Thermal conductivity of the elements10.1063/1.3253100 ↗
22. Thermal properties of graphene and nanostructured carbon materials10.1038/nmat3064 ↗
23. Effect of graphite flakes particle sizes on the microstructure and properties of graphite flakes/copper composites10.1016/j.jallcom.2018.06.129 ↗
24. The influence of SiC particle size and volume fraction on the thermal conductivity of spark plasma sintered UO2-SiC composites10.1016/j.jnucmat.2013.09.003 ↗
25. Thermophysical properties of uranium dioxide10.1016/S0022-3115(99)00273-1 ↗
26. The specific heat of graphite: an evaluation of measurements10.1016/0022-3115(73)90060-3 ↗
27. Graphite blocks with high thermal conductivity derived from natural graphite flake10.1016/j.carbon.2007.11.050 ↗
28. Chalk River Nuclear Laboratories in 1976. This report has no volume number and pages number except for one number AECL-5301.
29. Kinetic study of the UO2/C interaction by high-temperature mass spectrometry10.1016/j.nucengdes.2008.01.019 ↗
30. The thermal expansion of solid UO2 and (U, Pu) mixed oxides-a review and recommendations10.1016/0022-3115(88)90315-7 ↗
31. Thermal expansion coefficients of graphite crystals10.1016/0008-6223(72)90011-5 ↗
32. Graphite thermal expansion relationship for different temperature ranges10.1016/j.carbon.2005.06.009 ↗
33. Effective thermal conductivity of composites with interfacial thermal barrier resistance10.1177/002199838702100602 ↗