METHOD OF NUCLEAR FUEL SYNTHESIS FOR POWER FAST NEUTRON REACTORS WITH REACTOR CORE FROM MOLTEN SALT

摘要

FIELD: power engineering. ^ SUBSTANCE: invention relates to one of concepts to develop subsequent generations of power fast neutron reactors with nuclear fuel (NF) in a reactor core (RC) from molten uranium-containing chlorides. The method of nuclear fuel synthesis for power fast neutron reactors with a reactor core from a molten salt (mol. 1:1); KCl-UCl4. Uranium tetrachloride is introduced into initial melt of potassium chloride at 800C by means of anode dissolution of oxide-coal electrodes of uranium (UO2+C), containing 20% of carbon excess needed for the electrode reaction: UO2+C-4e=U4++CO2. ^ EFFECT: invention makes it possible to produce required compositions of chloride nuclear fuel that does not contain oxygen from simple triuranium octaoxides most available among oxides. ^ 3 cl