The U.S. Department of Energy is developing next generation processing methods to recycle uranium and transuranic (TRU) isotopes from spent nuclear fuel. The objective of the 3-year project described in this report was to develop near-term options for storing TRU oxides isolated through the uranium extraction (UREX+) process. More specifically, a Zircaloy matrix cermet was developed as a storage form for transuranics with the understanding that the cermet also has the ability to serve as an inert matrix fuel form for TRU burning after intermediate storage. The goals of this research projects were: 1) to develop the processing steps required to transform the effluent TRU nitrate solutions and the spent Zircaloy cladding into a zirconium matrix cermet storage form; and 2) to evaluate the impact of phenomena that govern durability of the storage form, material processing, and TRU utilization in fast reactor fuel. This report represents a compilation of the results generated under this program.