Methods of fluorides for reprocessing of spent fuels

Published data have been given in the paper dealing withe development of the fluoride method for reprocessina of spent nuclear fuels. These data had been published in 1977-19 80 in France, Japan, USSR and Czechoslovakia. Development of the technological process for reprocessing of the mixed fuel UO2-PuO2 has been practically finished. Now attention is paid to the design development of some apparatures. The technological process which had been proposed has been checked by means of reprocessing of the real spent fuel in pilot-pland scale. In this case yeald of U and Pu was nearly 99%. In laboratory scale the problem has been solved of removing from plutonium of ruthenium, which because of similar chemical reactions, poisoned Pu. Also the problem has been solved of isolation of U and transplutonium elements from the nonvotatile fission products in the medium of molten fluoride salts