Experience with the ammonium uranyl plutonyl carbonate coconversion process for mixed-oxide fuel fabrication

New reprocessing requirements asking for a solubility of mixed oxide fuel in nitric acid equal to that of uranium fuel led to the development of a new fabrication process. By coconverting a mixed nitrate solution of plutonium and uranium to a mixed oxide powder via an ammonium-uranyl-plutonyl carbonate precipitation this solubility is obtained already in the first process step. The new process minimizes dust production during powder handling and radiation exposure of the plant personnel and results in substantial improvements in regard to fuel quality and production costs. Process characteristics are described and the favorable properties of the resulting U, PuO/sub 2/-powder are given.