DocumentCode
1063781
Title
Micro-XANES and X-ray microtomography study of oxidation State, morphology, and chemistry evolution during nuclear fuel sintering
Author
Léchelle, J. ; Bleuet, P. ; Martin, P. ; Girard, E. ; Bruguier, F. ; Martinez, M.A. ; Somogyi, A. ; Simionovici, A. ; Ripert, M. ; Valdivieso, F. ; Goeuriot, P.
Author_Institution
Commissariat a l´´Energie Atomique, Centre d´´Etudes de Cadarache, St-Paul Lez Durance, France
Volume
51
Issue
4
fYear
2004
Firstpage
1657
Lastpage
1661
Abstract
Nuclear waste management has led to recycling PuO2 into mixed oxide fuel nuclear fuel (MOX). Its manufacturing route involves a sintering process. A multiscale model is under construction in order to predict the evolution of the sample characteristics during sintering and to improve sintering conditions. The purpose of the small scale model is to simulate grain size and chemistry evolution of micrometer large samples. In the green state, crystallites are 0.3 μm in size and are made either of UO2+x or of PuO2-y. After sintering (U,Pu)O2-z solid solutions are formed with crystalline grains close to 5 μm in size. At high temperature, sintering is governed by diffusion phenomena. Diffusion coefficients vary with point defect concentration. These defects are related to the oxidation state of the cations, the spatial distribution of which can be observed by means of micro X-ray absorption spectroscopy (XAS). Micro X-ray absorption near edge structure spectroscopy (micro-XANES) and high resolution X-ray microtomography study experiments have been performed at the European Synchrotron Radiation Facility beamline ID22, Grenoble. The applicability of these techniques has been demonstrated for testing simulation validity of (U, Pu)O2-z samples along the MOX sintering route.
Keywords
XANES; diffusion; oxidation; plutonium compounds; point defects; radioactive waste processing; sintering; tomography; uranium compounds; (U,Pu)O2-z solid solutions; European Synchrotron Radiation Facility beam line; ID22; MOX; PuO2-y; PuO2 recycling; UO2+x; UO2-PuO2; X-ray microtomography; chemistry evolution; crystallites; diffusion phenomena; grain size; green state; microX-ray absorption near edge structure spectroscopy; microX-ray absorption spectroscopy; microXANES; mixed oxide nuclear fuel; morphology; multiscale model; nuclear fuel sintering; nuclear waste management; oxidation state; plutonium dioxide; point defect concentration; sintering process; uranium dioxide; Chemistry; Crystallization; Electromagnetic wave absorption; Grain size; Morphology; Nuclear fuels; Oxidation; Radioactive pollution; Spectroscopy; Waste management;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/TNS.2004.832225
Filename
1323746
Link To Document