METHOD OF SEPARATING PLUTONIUM FROM URANIUM AND FROM OTHER TRANSURANIUM ELEMENTS

摘要

1378409 Separation of plutonium HAHNMEITNER-INSTITUT FUR KERNFORSCHUNG BERLIN GmbH 27 July 1972 [28 July 1971] 35214/72 Heading C7B In a process for separation of plutonium from uranium or from another transuranic element the electrolyte is dilute nitric acid solution of PuSPIV/SP or PuSPVI/SP with USPVI/SP or NpSPV/SP or a trivalent transuranic element with a complexing agent. Extraction is performed by the counter current and/or cross current ion migration processes. The complexing agent may be a carboxylic acid, a fluoride, a chelate former, a nitrate, a sulphate or a phosphate. The nitric acid may be 0À02-6N. Excess nitric acid may be removed by formic acid or formaldehyde. The cross current cell is divided into compartments by diaphragms and an ion selective membrane C. A mixture of acetic acid and nitric acid is introduced at 1, a complexing agent at 3 and the Pu, U mixture in nitric acid is introduced at 4. Uranium is continuously recovered at 2 and plutonium at 5. The electrolyte may be cooled.