Elaboration of Uranium Monocarbide Samples for Diffusion Studies

Author:

Fiquet O.1,Da-Silva L.1,Garcia-Ferre F.1,Brothier M.1,Carlot Gaëlle2,Garcia Philippe3,Martin Guillaume2,Barthe M.F.4

Affiliation:

1. CEA, DEN

2. CEA

3. Commissariat à l’Energie Atomique (CEA), DEN, DEC

4. CEMHTI

Abstract

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.

Publisher

Trans Tech Publications, Ltd.

Subject

Condensed Matter Physics,General Materials Science,Radiation

Reference10 articles.

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).

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.

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

Cited by 2 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Experimental study of UC polycrystals in the prospect of improving the as-fabricated sample purity;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2014-12

2. Quantitative ion beam analysis of M–C–O systems: application to an oxidized uranium carbide sample;Philosophical Magazine;2014-03-24

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