Radiation characteristics of spent nuclear fuel and wastes in nonaqueous reprocessing methods

The effect of the technology used to separate elements with nonaqueous radiochemical reprocessing of fuel on the radiation characteristics of the fuel and the wastes is examined. The study was conducted for the intrinsically safe BREST-1200 fast reactor. The conditions for achieving radiation equivalence between the raw material used for reactor operation and the wastes of the nuclear fuel cycle are indicated. The contribution of various nuclides to the potential biological hazard of wastes is examined for various holding periods. When the requirements imposed on the radiochemical technology are satisfied, the effect of the technological differences in the separation of individual elements from the spent fuel essentially did not greatly affect the results. 4 figures, 3 tables, 6 references.