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Thermal- and Radiation-enhanced Diffusion of Uranium in Oxidised Zirconium by N. Bérerd; N. Moncoffre; A. Chevarier; Y. Pipon; H. Faust; H. Catalette is a Engineering article available to read on EtoBox.

What is Thermal- and Radiation-enhanced Diffusion of Uranium in Oxidised Zirconium about?

This paper is devoted to the study of the defect influence on uranium diffusion in zirconia in the context of nuclear waste disposal. The experiments in reactor conditions are performed at the Institut Laue Langevin in Grenoble using the Lohengrin spectrometer. A thin UO 2 layer in direct contact with a zirconium foil is irradiated in the ILL high-flux reactor. The fission product rate is around 310 11 ions s À1 and the neutron flux is equal to 510 14 n cm À2 s À1 . The target temperature is controlled by an IR pyrometer and ranges from 470 to 490 8C. In these conditions, a zirconium oxidation is first observed before uranium diffusion. A model is proposed to deduce an apparent uranium diffusion coefficient in zirconia (ZrO 2 ) from the energy distribution broadening of a selected fission product (A=90). It is found to be equal to 10 À15 cm 2 s À1 . The study of thermal diffusion is performed by using ion beam techniques (ion implantation and Rutherford Backscattering). ZrO 2 samples are implanted with 800 keV uranium ions at a dose of 10 16 ions cm À2 and annealed at a pressure of 7.510 À1 Pa. No uranium diffusion could be observed up to 800 8C. The influence of irradiation def

Who reads Thermal- and Radiation-enhanced Diffusion of Uranium in Oxidised Zirconium?

Author

N. Bérerd; N. Moncoffre; A. Chevarier; Y. Pipon; H. Faust; H. Catalette

Publisher

Elsevier Science; Elsevier ; Elsevier BV (ISSN 0257-8972)

Published

2005

Language

LA

Field

Engineering (Physical Sciences)