Elaboration of Uranium Monocarbide Samples for Diffusion Studies


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Mixed Uranium-Plutonium Carbides are candidate fuels for 4th generation nuclear reactors. In this frame, a research program is underway at CEA (French alternative and atomic energies commission) to gather basic properties of such material to get a better understanding of in-pile behaviour. In the field of solid state physics, the measurement of transport properties and in particular diffusion coefficient requires the preparation of uranium carbide samples with very specific characteristics: very low oxygen content, mono-phased UC, high density (greater than 95% of the theoretical one), coarse microstructure, accurate samples geometry. In this paper the Process development is presented to manufacture such samples and the specific equipments which have been set up in glove-box. Characterizations of the first samples are also given.



Defect and Diffusion Forum (Volumes 323-325)

Edited by:

I. Bezverkhyy, S. Chevalier and O. Politano






O. Fiquet et al., "Elaboration of Uranium Monocarbide Samples for Diffusion Studies", Defect and Diffusion Forum, Vols. 323-325, pp. 253-259, 2012

Online since:

April 2012




[1] H. Matzke in Science of Advanced LMFBR fuels - A Monograph on Solid State Physics, Chemistry and Technology of Carbides, Nitrides and Carbonitrides of Uranium and Plutonium. JRC/ITU Karlsruhe - North-Holland (1986).

[2] M. Freyss, First-principles study of uranium carbide: Accommodation of point defects and of helium, xenon, and oxygen impurities. Phys. Rev. B 81, 014101 (2010).

DOI: 10.1103/physrevb.81.014101

[3] M. Pelletier, Refractory fuels for sodium fast reactors - Properties and irradiation behaviour. CEA/DEN/CAD/DEC/SESC/LSC (2009).

[4] H. Kleykamp, Fission product precipitates in irradiated uranium carbonitride fuel. Journal of Nuclear Materials Vol. 300 (2002) , pp.273-276.

DOI: 10.1016/s0022-3115(01)00741-3

[5] H. Kleykamp, Radial distribution of bonded fission gas in mixed carbide fuel pins. Journal of Nuclear Materials Vol. 80, (1979), pp.13-17.

DOI: 10.1016/0022-3115(79)90214-9

[6] H.R. Hoekstra, A. Santoro, S. Siegel, Journal of Inorg. Nucl. Chem. 18 (1961) p.166.

[7] Martin G, Desgardin P, Sauvage T, Garcia P, Carlot G, Khodja H, et al. A quantitative µNRA study of helium intergranular and volume diffusion in sintered UO2. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 2006; 249(1-2): 509-12.

DOI: 10.1016/j.nimb.2006.03.042

[8] Martin G, Sauvage T, Desgardin P, Garcia P, Carlot G, Barthe MF. Accurate automated non-resonant NRA depth profiling: Application to the low 3He concentration detection in UO2 and SiC. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 2007; 258(2): 471-8.

DOI: 10.1016/j.nimb.2007.01.288

[9] Pickles S. The sintering of Uranium carbide and of Uranium-pluonium carbide and the role of Nickel as a sintering additive. Journal of Nuclear Materials. 1980; 89(1): (1980).

DOI: 10.1016/0022-3115(80)90062-8

[10] Ganguly. Sintering behaviour of Plutonium rich (UPu)C and (UPu)CN pellets Transaction of the PMAI 1980; 7.

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