PROCESS FOR RECOVERY OF URANIUM AND TRANSURANIAN ELEMENTS FROM WASTE NUCLEAR FUEL

摘要

The process comprises the steps of: dissolving the spent nuclear fuel in nitric acid (S 100), - subjecting the resulting solution to electrolytic oxidation (S 102) - cooling the solution after electrolytic oxidation (S 104) , - co-precipitate the nitrates of uranium and transuranic elements with uranyl nitrate - redissolve in nitric acid (S 106) the uranyl nitrate and the nitrates of uranium and transuranic elements coprecipitated, - cool the mixed solution thus obtained (S 108) selectively precipitate uranyl nitrate and filter this uranyl nitrate, - redissolve the filtered uranyl nitrate in nitric acid to thus prepare a solution of uranyl nitrate (S 112), - subject the resulting mixed solution to electrolytic oxidation (S 116) and, - cool the mixed solution after electrolytic oxidation, and co-precipitate the nitrates of uranium and transuranic elements with uranyl nitrate prov enant of the mixture (S 118).