Fuel breeding in the blanket of a hybrid mesocatalytic reactor

Burnup of nuclear fuel, plutonium breeding under conditions of d-t fusion the uranium blanket of a hybrid mesocatalytic reactor are discussed. For the purpose of plutonium production which is used in nuclear thermal reactors several fuel management schemes were considered. The changing of the nuclide concentrations with time of fuel irradiation was calculated by the code BURNFL. Using the three-dimensional Monte Carlo code MORSE-H the plutonium and tritium breeding coefficients, the number of fissions of uranium and plutonium the neutron spectra and the power distribution in the blanket during the fuel irradiation were calculated. 40 refs.; 16 figs.; 5 tabs