Gas-fluoride technology for processing spent oxide fuel

The scientific-research work on reprocessing spent oxide fuel by gas fluori de method is reviewed The refining possibilities of the basic stages of gas fluoride technology are studied The possibility of separating most fission products front the ashes at the fluoridation stage is confirmed experiment ally. The use of fluoride sorbents (NaF, BaF2) permits reaching a total coe fficient of removal of fission: products front UF6 at the 10(7) level. It i s shown. that deep extraction of plutonium from oxide fuel is possible. The results of investigations or: pyrohydrolysis of UF6 and a mixture of UF6 w ith PuF6 with production: of granulate of the oxides with the required dens ity with fluorine content 0.005 mass % and oxygen coefficient 2-2.1 are pre sented. Recommendations for use of gas fluoride technology for reprocessing spent oxide fuel front fast and light-water reactors are giver? taking acc ount of the new requirements for nonproliferation of fissioning materials, and a prediction is giver: for a closed nuclear fuel cycle using gas-fluori de technology and separation of Np, Ain, and Cm for transmutation with the aid of easily melting fluoride melts: 1 figure, 5 tables, 27 references.