Abstract
A significant quantity of plutonium bearing scrap was getting generated during the fabrication of (U,Pu)O2 mixed oxide fuel for Indian Prototype Fast Breeder Reactor. This document assesses the feasibility of carrying out recycling of the impure scrap to permit the efficient plutonium recovery and re-use. The impure scrap which constitutes nearly 5 % of the total throughput was examined for impurities present and dissolution behaviour in HNO3. On the basis of experimental results obtained recycling methodologies are recommended. This study reveals that not all types of the impure scrap need aqueous recycling methods; some can be dry recycled.