volume 440 issue 1-3 pages 546-552

Influence of the Oxygen content on the thermal migration of Xenon in ZrCxO1−x

Y. Pipon 1
N Toulhoat 2, 3
N Moncoffre 3
G. Gutierrez 4
A. Maître 5
M Gendre 5
2
 
Commissariat à l’Energie Atomique CEA/DEN, Centre de Saclay, 91191 Gif sur Yvette Cedex, France
4
 
Institut d’Électronique du Solide et des Systèmes (InESS), 23, rue du Lœss, BP 20 CR, 67037 Strasbourg Cedex 2 Strasbourg, France
5
 
Laboratoire Science des Procédés Céramiques et Traitements de Surface, UMR CNRS 6638, Centre Européen de la Céramique, 12, rue Atlantis, 87068 Limoges Cedex, France
Publication typeJournal Article
Publication date2013-09-01
scimago Q1
wos Q1
SJR0.984
CiteScore6.2
Impact factor3.2
ISSN00223115, 18734820
General Materials Science
Nuclear and High Energy Physics
Nuclear Energy and Engineering
Abstract
Zirconium carbide (ZrC) is a refractory ceramic presenting interesting properties such as a high melting point, a very high hardness and a good thermal stability. For these reasons, this material is considered as a candidate for fuel coating for fourth-generation reactors in particular for the Gas cooled Fast Reactors (GFR). The ceramic temperature could reach 1200 °C in normal reactor operation and reach 1700 °C in accidental conditions. It is therefore important to assess the ZrC thermal retention capacity regarding abundant and/or volatile fission products. This paper deals with the behavior of Xenon which is the major gaseous fission product created during fission. Previous studies have shown that Xenon remained motionless in an “Oxygen-poor” matrix such as ZrC 0.95 O 0.05 , up to temperatures of 1800 °C. However, Zirconium oxycarbides are known to be very sensitive to oxidation. This study aims therefore at studying the behavior of Xenon in Zirconium oxycarbide samples with different Oxygen contents. Xenon is introduced by ion implantation and the samples are annealed in secondary vacuum in the temperature range 1400 °C–1800 °C. The Oxygen profiles are determined by using the 16 O( 4 He, 4 He) 16 O nuclear reaction at 7.5 MeV and the concentration profiles of Xenon are measured by Rutherford Backscattering Spectrometry at each step of the treatment. The results show that the behavior of the material during annealing with respect to oxidation is strongly related to its initial Oxygen content. More generally, the higher the initial Oxygen content, the more important is the oxidation. Consequently, the Xenon migration is enhanced in Oxygen rich Zirconium carbides.
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Pipon Y. et al. Influence of the Oxygen content on the thermal migration of Xenon in ZrCxO1−x // Journal of Nuclear Materials. 2013. Vol. 440. No. 1-3. pp. 546-552.
GOST all authors (up to 50) Copy
Pipon Y., Toulhoat N., Moncoffre N., Gutierrez G., Maître A., Gendre M. Influence of the Oxygen content on the thermal migration of Xenon in ZrCxO1−x // Journal of Nuclear Materials. 2013. Vol. 440. No. 1-3. pp. 546-552.
RIS |
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RIS Copy
TY - JOUR
DO - 10.1016/j.jnucmat.2013.03.015
UR - https://doi.org/10.1016/j.jnucmat.2013.03.015
TI - Influence of the Oxygen content on the thermal migration of Xenon in ZrCxO1−x
T2 - Journal of Nuclear Materials
AU - Pipon, Y.
AU - Toulhoat, N
AU - Moncoffre, N
AU - Gutierrez, G.
AU - Maître, A.
AU - Gendre, M
PY - 2013
DA - 2013/09/01
PB - Elsevier
SP - 546-552
IS - 1-3
VL - 440
SN - 0022-3115
SN - 1873-4820
ER -
BibTex |
Cite this
BibTex (up to 50 authors) Copy
@article{2013_Pipon,
author = {Y. Pipon and N Toulhoat and N Moncoffre and G. Gutierrez and A. Maître and M Gendre},
title = {Influence of the Oxygen content on the thermal migration of Xenon in ZrCxO1−x},
journal = {Journal of Nuclear Materials},
year = {2013},
volume = {440},
publisher = {Elsevier},
month = {sep},
url = {https://doi.org/10.1016/j.jnucmat.2013.03.015},
number = {1-3},
pages = {546--552},
doi = {10.1016/j.jnucmat.2013.03.015}
}
MLA
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Pipon, Y., et al. “Influence of the Oxygen content on the thermal migration of Xenon in ZrCxO1−x.” Journal of Nuclear Materials, vol. 440, no. 1-3, Sep. 2013, pp. 546-552. https://doi.org/10.1016/j.jnucmat.2013.03.015.