Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1566532 | Journal of Nuclear Materials | 2011 | 5 Pages |
Abstract
Transition metal carbides, such as ZrC, are interesting candidates used as structural and fuel cladding materials for the 4th generation Gas cooled Fast Reactors. A study has been carried out to elucidate the role of temperature on the diffusion of xenon in zirconium carbide. For that purpose, zirconium oxycarbide samples (ZrC0.95O0.05) have been prepared from powders synthesized by carbothermal route and sintered by Spark Plasma Sintering at 2125Â K. Two batches have been studied in order to evaluate the role of the presence of free carbon and zirconia during high temperature annealing. The composition and microstructural features of the sintered samples such as stoichiometry, density and grain size have been determined using complementary analytical techniques such as Nuclear Backscattering Spectrometry, Electron Microscopy and elementary chemical analysis. Ions of 136Xe2+ have been implanted at an energy of 800Â keV corresponding to a mean projected range of 160Â nm and at an ion fluence of 1016Â cmâ2 corresponding to a maximum concentration of 1Â at.%. Thermal annealing has been carried out in a temperature range from 1775 to 2075Â K. The xenon distribution profiles have been measured by Rutherford Backscattering Spectrometry before and after the different treatments. The results show that the presence of residual zirconia induces a strong damage of the surface and that pure ZrC sintered specimen display less degradation of the surface and better retention capabilities for xenon.
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Authors
G. Gutierrez, N. Toulhoat, N. Moncoffre, Y. Pipon, A. Maître, M. Gendre, A. Perrat-Mabilon,