Modelling Fission Gas Bubble Distribution in UO2

Richard Skorek; Serge Maillard; Amélie  Michel; Gaëlle Carlot; Eric Gilabert; Thomas Jourdan

doi:10.4028/www.scientific.net/DDF.323-325.209

Paper Titles

Surface Blistering and Flaking of Sintered Uranium Dioxide Samples under High Dose Gas Implantation and Annealing
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A TEM Study of Bubbles Growth with Temperature in Xenon and Krypton Implanted Uranium Dioxide
p.191

Iodine Volume Diffusion Measurements in Uranium Dioxide
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Towards Measuring the Pu Self-Diffusion Coefficient in Polycrystalline U_0.55Pu_0.45O_2±x
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Modelling Fission Gas Bubble Distribution in UO₂
p.209

Molecular Dynamics Study of Grain Boundary Diffusion of Fission Gas in Uranium Dioxide
p.215

Helium Behaviour in Fe-Base Materials: Thermal Desorption and Nuclear Reaction Analyses
p.221

Specific Aspects of Internal Corrosion of Nuclear Clad Made of Zircaloy
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A Density Functional Study of Oxygen Mobility in Ceria-Based Materials
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HomeDefect and Diffusion ForumDefect and Diffusion Forum Vols. 323-325Modelling Fission Gas Bubble Distribution in UO2

Modelling Fission Gas Bubble Distribution in UO₂

Abstract:

The Cluster Dynamics method is assessed for the investigation of fission gas behaviour in a krypton-implanted and annealed UO₂ sample. The simulation results are then compared to Thermal Desorption Spectroscopy (TDS) data. A release mechanism is proposed: the initial burst is related to krypton migration via an interstitial mechanism, while the second stage of the release process can be accounted for by the diffusion of krypton in a substitutional position. This latter mechanism is compatible with a diffusion coefficient of 4.10^-21m²/s.

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Defect and Diffusion Forum (Volumes 323-325)

Pages:

209-214

DOI:

https://doi.org/10.4028/www.scientific.net/DDF.323-325.209

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Online since:

April 2012

Authors:

Richard Skorek, Serge Maillard, Amélie Michel, Gaëlle Carlot, Eric Gilabert, Thomas Jourdan

Keywords:

Cluster Dynamics, Fission Gas Release, Nuclear Fuel, Rate Theory, Thermal Desorption Spectroscopy

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References

[1] C. Struzik, M. Moyne and J.P. Piron, in: Proc. 1997 Int. Topical Meeting on Light Water Reactor Fuel Performance, Portland, Oregon USA (1997), p.126.

Google Scholar

[2] G. Kaganas and J. Rest: A physical description of ﬁssion product behavior in fuels for advanced power reactors (2007).

DOI: 10.2172/919331

Google Scholar

[3] L. Noirot, in: Nuclear Engineering and Design, Corrected Proof (2011), in press.

Google Scholar

[4] M.H. Wood: Journal of Nuclear Materials 82 (1979), pp.257-263.

Google Scholar

[5] J.M. Griesmeyer and N.M. Ghoniem: Journal of Nuclear Materials 80 (1979), pp.88-101.

Google Scholar

[6] A. Barbu and E. Clouet: Solid State Phenomena 129 (2007), pp.51-58.

Google Scholar

[7] A.E. Volkov and A.I. Ryazanov: Journal of Nuclear Materials 273 (1999), pp.155-163.

Google Scholar

[8] G. Martin, P. Garcia, C. Sabathier, L. Van Brutzel, B. Dorado, F. Garrido and S. Maillard: Physics Letters A 374 (2010), pp.3038-3041.

DOI: 10.1016/j.physleta.2010.05.033

Google Scholar

[9] X. -Y. Liu, B.P. Uberuaga, D.A. Andersson, C.R. Stanek and K.E. Sickafus: Appl. Phys. Lett. 98 (2011).

Google Scholar

[10] B. Dorado, in: Etude des propriétés de transport atomique dans le dioxyde d'uranium par le calcul de structure électronique: influence des fortes corrélations, PhD Thesis Univ. Aix Marseille (2010).

Google Scholar