2014
DOI: 10.1016/j.jnucmat.2013.12.014
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Controlling the oxygen potential to improve the densification and the solid solution formation of uranium–plutonium mixed oxides

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Cited by 23 publications
(17 citation statements)
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“…The second peak between 300 and 600°C is directly linked to the reduction of UO 2+x into UO 2,00 [4]. A third smaller peak appears around 900°C which also results from the reduction process of UO 2+x into UO 2,00 .…”
Section: Resultsmentioning
confidence: 92%
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“…The second peak between 300 and 600°C is directly linked to the reduction of UO 2+x into UO 2,00 [4]. A third smaller peak appears around 900°C which also results from the reduction process of UO 2+x into UO 2,00 .…”
Section: Resultsmentioning
confidence: 92%
“…The latter sets the nature and the concentration of point defects which govern diffusion mechanisms inside the material [2]. The oxygen partial pressure, pO 2 , of the sintering gas in equilibrium with MOX pellets needs to be precisely controlled; otherwise it may induce a large dispersion in the critical parameters for fuel manufacturing [2][3][4]. Among these parameters, the oxygento-metal ratio (O/M) after sintering defines many properties of the fuel in operation (thermal conductivity, mechanical properties, fuel-cladding interaction, etc.).…”
Section: Introductionmentioning
confidence: 99%
“…It appears that densification begins at lower temperatures within oxidizing atmospheres. Recently, Berzati et al [13,14] confirmed this result on UO 2 -30% PuO 2 mixtures and showed that both densification and solid solution formation occur at a lower temperature when the oxygen potential increases. The effect of plutonium concentration on the relationship between sintering http://dx.doi.org/10.1016/j.jeurceramsoc.2015.05.006 0955-2219/© 2015 Elsevier Ltd. All rights reserved.…”
Section: Introductionmentioning
confidence: 73%
“…Sodium-cooled fast reactors (SFRs) are envisaged in France and an experimental prototype, ASTRID, is being currently under development [12]. Mixed uranium-plutonium oxide (MOX) fuel with plutonium content close to 30% is considered as candidate fuel for such reactor, and the research work regarding its fabrication is under progress [13][14][15][16][17].…”
Section: Introductionmentioning
confidence: 99%
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