METHOD FOR PURIFYING NITROGEN ACID SOLUTIONS FROM AMERICIUM Russian patent published in 2021 - IPC C22B60/02 C01G56/00 

FIELD: radiochemistry.

SUBSTANCE: invention relates to radiochemical technology and can be used for purification of raffinate from americium obtained during extraction refining of plutonium in production of mixed uranium-plutonium fuel. Purification of nitric acid solutions from americium includes coprecipitation of americium oxalate from solutions containing compounds of related metals by introducing a carrier and oxalic acid, holding the pulp to form a precipitate, washing the resulting precipitate, separating the precipitate from the mother liquor and subsequent calcination to a mixture of oxides containing americium. Before the introduction of the carrier, a salt-free reducing agent is introduced into the nitric acid solution, uranium (IV) is added as a carrier, which is introduced into the system in the form of a nitric acid solution stabilized with hydrazine until the concentration of uranium (IV) in the final pulp is at least 1 g / L.

EFFECT: method allows to simplify the technological process by expanding the working range of the content of nitric acid in the initial solution during the deposition operation, to reduce the americium content in the initial nitric acid solution in one operation of co-precipitation with uranium oxalate by more than 9 - 103 times and to obtain a mixture of uranium and americium oxides , suitable for use in the composition of molten salt reactor fuel.

4 cl, 1 dwg, 2 ex