Radiation characteristics of REMIX fuel during multiple recycling in VVER-1000 reactors

Changes in the isotopic composition of three REMIX fuel types in the process of operation in a VVER-1000 reactor have been calculated. It has been shown that it is possible to recycle REMIX-A and REMIX-A2 fuel more than five times without a major decrease in its nuclear value. The equivalent dose rate from fresh REMIX fuel assemblies has been calculated depending on the recycle number and the fresh fuel decay time after fabrication. The relative contribution of different radionuclides to the equivalent dose rate has been analyzed. The calculation results for the buildup of 232U and even Pu isotopes depending on the fuel recycle number are presented.