2013
DOI: 10.1016/j.jnucmat.2013.01.351
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Restructuring and redistribution of actinides in Am-MOX fuel during the first 24h of irradiation

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Cited by 17 publications
(3 citation statements)
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“…Figure 79 shows the radial distribution of U and Pu, as well as the Am and Np produced by capture. The enrichment of Pu towards the central void is consistent with the Soret effect predicted for SFR MOX fuels and readily observed in literature [33][34][35]. The signal becomes scattered toward the fuel periphery.…”
Section: Actinides and Fission Products Radial Redistribution Measured By Epmasupporting
confidence: 90%
“…Figure 79 shows the radial distribution of U and Pu, as well as the Am and Np produced by capture. The enrichment of Pu towards the central void is consistent with the Soret effect predicted for SFR MOX fuels and readily observed in literature [33][34][35]. The signal becomes scattered toward the fuel periphery.…”
Section: Actinides and Fission Products Radial Redistribution Measured By Epmasupporting
confidence: 90%
“…More-over, the inclusion of the equations governing the plutonium, americium, and oxygen redistribution is of interest, in order to account for the effects of such quantities on the thermal and porosity solutions. Finally, once these modeling advancements will be available, we envisage a validation of the model against separate effect tests focused on the pore velocity model, e.g., comparing to the data from the Am-1 experiment [38], and a integral validation of the pore migration model, once it will be included in the GERMINAL/PLEIADES fuel performance code, against other Phenix irradiation data.…”
Section: Discussionmentioning
confidence: 99%
“…Several research programs have been dedicated to investigating the transmutation of MAcontaining transmutation targets by looking at different fabrication routes, the in-reactor behavior and post-irradiation examinations [3][4][5][6]. Particular effort is put on the development of fabrication routes to address various needs such as the type of host matrix and content of the MA element, the physico-chemical properties of the target material, and reduced radiological hazards during handling [7].…”
Section: Introductionmentioning
confidence: 99%