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Processing transuranium isotopes: Waste characterization and implications for process improvements

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6775791
Liquid, gaseous, and solid wastes generated by processing transuranium elements were characterized to determine improvements needed to minimize waste volumes and simplify treatment and disposal. Most of the western world's supply of {sup 249}Bk, {sup 252}Cf, {sup 253}Es, and {sup 257}Fm is produced in the U.S. Department of Energy's Transuranium Element Processing Program at Oak Ridge National laboratory (ORNL). This program utilizes the High Flux Isotope Reactor (HFIR) and the Radiochemical Engineering Development Center (REDC). Aluminum-clad targets containing {approximately}10 g of {sup 242}Pu or americium and curium, as an oxide-aluminum cermet, are irradiated in HFIR and processed in the REDC to recover transuranium elements and fabricate new targets. Typically, a group of {approximately}13 targets is processed in a campaign that is begun {approximately}3 weeks after discharge from HFIR. The steps used to process irradiated targets are described. Characteristics of liquid wastes from a typical campaign are summarized. Characterization of wastes was necessary to identify and prioritize process improvements that offer significant potential to minimize volumes and simplify treatment and disposal.
OSTI ID:
6775791
Report Number(s):
CONF-891103--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
Country of Publication:
United States
Language:
English