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Development of an Engineered Producet Storage Concept for the UREX+1 Combined Transuraqnic?Lanthanide Product Streams
Author(s) -
Sean M. McDeavitt,
Thomas J. Downar,
T. A. Taiwo,
Mark A. Williamson
Publication year - 2009
Language(s) - English
Resource type - Reports
DOI - 10.2172/948872
Subject(s) - cermet , spent nuclear fuel , cladding (metalworking) , enriched uranium , waste management , uranium , nuclear fuel , environmental science , process engineering , engineering , materials science , nuclear engineering , metallurgy , ceramic
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 a 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 Xircaloy cladding into a zireonium matrix cermet sotrage form; and 2) to evaluate the impact of phenomena that govern durability of the storage form, material processing, and TRU utiliztion in fast reactor fuel. This report represents a compilation of the results generated under this program. The information is presented as a brief technical narrative in the following sections with appended papers, presentations and academic theses to provide a detailed review of the project's accomplishments

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