Nuclear fuel recovery - from mixt with silicon carbide by high temp chlorination and oxidn

摘要

Recovery of nuclear fuel, encapsulated in or combined in some other way with SiC, comprises treatment with Cl2 at 1000 degrees C to remove the SiC and oxidn to remove the C from the residue of the remaining coated fuel. Technique can be used to recover fuel from mfg. waste or from irradiated fuel, e.g. as used in high temp. gas cooled reactors. Treatment is suitable for coated fuel and also mouldings with SiC matrix and opt. container for fuel element.