On the Dissolution of (U,Pu)O₂Solid Solutions with Different Plutonium Contents in Boiling Nitric Acid

Direct sintering of UO2+x oxides prepared under hydrothermal conditions

“…In order to face these technological challenges, the manufacturing of the fuel ceramic has to be optimized. Especially, homogeneous mixed oxides should be favoured to prevent the existence of Pu-enriched hot spots during in-core lifetime, that can also become refractory towards dissolution during the reprocessing step [6]. On this basis, if processes based on powder metallurgy have been studied for long (for example with the COCA process in France) [7], numerous studies also considered wet chemistry methods to precipitate homogeneous precursors (i.e.…”

Impurity analysis and dissolution behaviour of plutonium bearing impure MOX scrap: an assessment of recycling feasibility

“…(U,Pu)O 2 solid solution has inherent characteristic for achieving an adequate plutonium solubility during dissolution in HNO 3 without dissolution aids or catalyst. This is practically observable up to 35 wt% of PuO 2 in the MOX, beyond which again solid solution leave behind residue rich in plutonium [21,22]. The remaining residue is due to presence of difficult to dissolve PuO 2 agglomerates or Pu rich MOX.…”

“…This is noteworthy that the reprocessing facilities avoid use of the fluoride (being corrosive) for the dissolution and mechanically blended or non-sintered (UO 2 ? PuO 2 ) mixtures cannot be dissolved quantitatively [21][22][23]. Thus it was planned to set-up an inhouse recycling facility at AFFF.…”

Dissolution of mixed oxide(MOX) fuel in nitric acid:A review

“…However, if the amount of plutonium (Pu) in MOX fuel is relatively small, it can still dissolve into nitric acid and the reactions are shown in Equations (4) , (5) , (6) . On the contrary, if the Pu content is excessively high, the solubility significantly decreases [ 50 ]. …”