526e Lab-Scale Demonstration of the Urex+1a Process Using Spent Nuclear Fuel

Candido Pereira, George F. Vandegrift, Monica C. Regalbuto, Allen J. Bakel, Delbert L. Bowers, and James J. Laidler. Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439

The Global Nuclear Energy Partnership (GNEP) is developing technologies to greatly expand repository capacity, improve proliferation resistance, and recover valuable energy that would otherwise be discarded; thus assuring a stable energy supply for the future. An important element of this initiative is the separation of key radionuclides followed by either superior waste-disposal forms and/or transmutation of long-lived isotopes. To that end, the GNEP is developing advanced fuel reprocessing systems that separate key radionuclides from spent fuel. One of these systems is the UREX+1a process. The UREX+1a process is a series of four solvent-extraction flowsheets that perform the following operations: (1) recovery of U and Tc (UREX), (2) recovery of Cs and Sr (CCD-PEG), and (3) recovery of TRU and rare earth elements (TRUEX), and (4) separation of TRU elements from the rare earths (TALSPEAK). This paper discusses the results of the demonstration of the UREX, TRUEX, and TALSPEAK processes using spent nuclear fuel, as well as future development needs and plans. Research funded by U.S. Department of Energy, Office of Nuclear Energy, Science and Technology.