DocumentCode :
1814524
Title :
μ-XANES and X-ray μ-tomography 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 :
Centre d´´Etudes de Cadarache, St-Paul Lez Durance, France
Volume :
2
fYear :
2003
fDate :
19-25 Oct. 2003
Firstpage :
772
Abstract :
Nuclear waste management has led to recycling PuO2 into nuclear fuel (Mixed OXides). Its manufacturing route involves a sintering process. A model is under construction in order to predict the evolution of the sample characteristics during sintering and to improve the sintering conditions. The small scale model aims to simulate grain size and chemistry evolution of μm large samples. In the green state, crystallites are 0.3 μm in size and made either of UO2+x or of PuO2-y. After sintering their size is close to 5μm and they have become a solid solution (U,Pu)O2-z. 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 g-X-Ray Absorption Spectroscopy (XAS). μ-XANES (X-Ray Absorption Near Edge Spectroscopy) and μ-X-Ray tomography pre-study experiments carried out at the ESRF (European Synchrotron Radiation Facility) ID22, Grenoble, have shown the ability of these techniques for such samples. It may be used to observe (U, Pu)O2-z samples chosen along the sintering route, to check simulation validity.
Keywords :
X-ray absorption spectra; XANES; fission reactor fuel reprocessing; grain size; plutonium compounds; point defects; radioactive waste processing; sintering; tomography; uranium compounds; μ-XANES; 0.3 micron; 5 mm; Mixed OXides fuel; PuO2-y; PuO2; UO2+x; X-Ray Absorption Near Edge Spectroscopy; X-ray μ-tomography; chemistry evolution; morphology; nuclear fuel sintering; nuclear waste management; oxidation state; recycling PuO2; simulate grain size; Chemistry; Electromagnetic wave absorption; Grain size; Morphology; Nuclear fuels; Oxidation; Radioactive pollution; Recycling; Spectroscopy; Waste management;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Nuclear Science Symposium Conference Record, 2003 IEEE
ISSN :
1082-3654
Print_ISBN :
0-7803-8257-9
Type :
conf
DOI :
10.1109/NSSMIC.2003.1351812
Filename :
1351812
Link To Document :
بازگشت