Purification of Uranium Fuels by Slagging and Filtratiop

Abstract

Using uranium containing 0·1 per cent cerium as a simple model of irradiated fuel, the degree of ‘poison’ removal by selfslagging methods has been found to be comparable with that achieved at very low alloying concentrations. By filtration through oxide beds, removals of 95 per cent Ce have been obtained, the speed of processing being limited only by the time required to reach operating temperature.

Some information is presented on the behaviour of inclusions and the mechanism of cerium removal from the alloys.