Method for wet dissolving of nuclear fuels of uranium-plutonium mixed oxide

摘要

In a process which avoids the corrosion problems which it has hitherto been necessary to minimise, simplifies offgas treatment and greatly reduces the complexity with respect to the plant and procedure required and also greatly reduces the costs, the nuclear fuel is treated with an aqueous solution containing HCO3- ions or HCO3- ions and CO3-- ions, with or without an oxidising, dissolved dissolution aid.