Correcting the isotopic composition of regenerated uranium with respect to (232)U by a centrifuge method with introduction of a carrier gas

Theoretical and experimental studies dealing with correcting the isotopic composition of regenerated uranium with respect to (232)U by a centrifuge method with introduction of a carrier gas are reported. In order to increase the efficiency of separating (232)U from the spent uranium and reduce the loss of (235)U, the use of a carrier gas is proposed - the gaseous compound (12)C(8)H(3 )F(13), which is inert to uranium hexafluoride, and whose molecular weight, M(c)=346amu, matches that of (232)UF(6). Freon, C(8)H(3)F(13[/s ubscript], is shown not to decompose during operation in the rotor of a centrifuge or to interact with the centrifuge material. The measured absorption parameters of freon on sodium fluoride NaF confirm the feasibility of efficient separation of a mixture of uranium hexafluoride and freon with return of the freon to the separation process. It is shown that introducing a carrier gas into the centrifuge technology can yield some new results: lowering the radioactivity of the commercial product, normalizing the overall radiation situation during production, increasing the recovered (235)U in the commercial product, and reducing the volume of radioactive waste. The recovery of (235)U in the commercial product can be increased to 99% or more. Then the (232)U content in the commercial product is 2.10(-8)% or a factor of 10 less than the maximum allowable content of 2.10(-7)%.