Patent ID: 9147502
Filing Date: 2015-09-29
Classification: C22B,G21C,G21F,Y02E,Y02W

Abstract:
1. A method of volumetric oxidative treatment of spent nuclear fuel (SNF) of uranium dioxide, the method comprising thermal processing a reaction mass of SNF element fragments in oxidative environment, said thermal processing being carried out in at least one reaction chamber in two phases, the first phase being performed at 400-650° C. for 60-360 minutes in the gas stream of air additionally comprising carbon dioxide in the amount of 1-4 volume %, the second phase being performed at 350-450° C. for 30-120 minutes in the gas stream of air that includes water steam in the amount corresponding to the dew point of gas-vapor mixture at 30-40° C., the both phases being performed with a repeated mechanical activation of the reaction mass.