International audienceCo-management of the actinides in an integrated closed fuel cycle by a pyrochemical process is studied at the laboratory scale in France in the CEA-ATALANTE facility. In this context the co-precipitation of U(III) and Pu(III) by wet argon sparging in LiCl-CaCl2 (30–70 mol%) molten salt at 705 °C is studied. Pu(III) is prepared in situ in the molten salt by carbochlorination of PuO2 and U(III) is then introduced as UCl3 after chlorine purge by argon to avoid any oxidation of uranium up to U(VI) by Cl2. The oxide conversion yield through wet argon sparging is quantitative. However, the preferential oxidation of U(III) in comparison to Pu(III) is responsible for a successive conversion of the two actinides, giving a mixtu...
Uranium oxides in a molten eutectic mixture of NaClKCl were chlorinated by bubbling chlorine gas thr...
International audiencePyrochemical technology using high-temperature molten salts and molten metal m...
The electrochemical behavior of plutonium fluoride species was investigated in molten LiF-CaF2 mediu...
International audienceCo-management of the actinides in an integrated closed fuel cycle by a pyroche...
International audienceIn the context of pyrochemical processes for nuclear fuel treatment, the preci...
L’étude réalisée au cours de cette thèse concerne la synthèse d’oxydes d’actinides en fin de procédé...
A chlorination route is being investigated for recovery of actinides from actinide–aluminium alloys,...
Pyrochemical processes in molten LiCl–KCl are being developed in ITU for recovery of actinides from ...
A chlorination route is being investigated for recovery of actinides from actinide-aluminium alloys,...
International audienceThe uranium and plutonium co-conversion process constitutes a continuous subje...
AbstractMuch attention has been paid to the handling of metallic nuclear fuel, which can offer a saf...
Uranium oxides in a molten eutectic mixture of NaClKCl were chlorinated by bubbling chlorine gas thr...
International audiencePyrochemical technology using high-temperature molten salts and molten metal m...
The electrochemical behavior of plutonium fluoride species was investigated in molten LiF-CaF2 mediu...
International audienceCo-management of the actinides in an integrated closed fuel cycle by a pyroche...
International audienceIn the context of pyrochemical processes for nuclear fuel treatment, the preci...
L’étude réalisée au cours de cette thèse concerne la synthèse d’oxydes d’actinides en fin de procédé...
A chlorination route is being investigated for recovery of actinides from actinide–aluminium alloys,...
Pyrochemical processes in molten LiCl–KCl are being developed in ITU for recovery of actinides from ...
A chlorination route is being investigated for recovery of actinides from actinide-aluminium alloys,...
International audienceThe uranium and plutonium co-conversion process constitutes a continuous subje...
AbstractMuch attention has been paid to the handling of metallic nuclear fuel, which can offer a saf...
Uranium oxides in a molten eutectic mixture of NaClKCl were chlorinated by bubbling chlorine gas thr...
International audiencePyrochemical technology using high-temperature molten salts and molten metal m...
The electrochemical behavior of plutonium fluoride species was investigated in molten LiF-CaF2 mediu...