Kristy M. Long

Uranium/technetium separation for the UREX process - synthesis and characterization of solid reprocessing forms

Abstract In the context of the demonstration of the UREX (uranium extraction) process, a separation of uranium and technetium using an anion exchange resin was performed on a simulant solution containing 98.95 g/L of 238U and 130.2 mg/L of 99Tc. After sorption on the resin, TcO4− was eluted with NH4OH, the eluting stream was treated, and the technetium converted to Tc metal (yield=52.5%). The purity of the compound was analyzed: it contains less than 23.8 μg of 238U per gram of 99Tc. Tc metal was characterized by X-ray diffraction (XRD) and X-ray absorption fine structure (XAFS) spectroscopy; EXAFS analysis clearly confirms the hexagonal structure of the metal obtained after treatment. Uranium was converted to ammonium diuranate and to U3O8 in a yield of 88.2%, analysis indicates that the compound contains less than 0.16 μg of 99Tc per gram of ammonium diuaranate.

Separation of Pertechnetate from Uranium in a Simulated UREX Processing Solution Using Anion Exchange Extraction Chromatography

A process to separate technetium from uranium in a simulated process solution resulting from the uranium extraction (UREX) process was demonstrated using a new extraction chromatographic (EC) resin from Eichrom Technologies. The Weak Base ECTM resin contains a tertiary amine incorporated into a macroporous resin bead support. The resin provided a good separation of pertechnetate from a 100 g/L uranyl(VI) nitrate solution representative of a UREX feed solution. The resin appeared quite stable to multiple uses. The elution of Tc from the resin was substantially improved over previous anion exchangers used. The eluted pertechnetate and ammonium nitrate solution was mixed with a reducing agent and gradually heated under an argon flow and then an argon/H2O flow to recover the Tc as the metal (96% yield). The U was precipitated with ammonium hydroxide and recovered as U3O8 (98% yield).

Photochemical oxidation of oxalate in Pu-238 process streams

For over forty years, NASA has relied on plutonium-238 in Radioisotope Thermoelectric Generator (RTG) units and Radioisotope Heater Units ( W s ) to provide power and heat for many space missions including Transit, Pioneer, Viking, Voyager, Galileo, Ulysses and Cassini. RHUs provide heat to keep key components warm in extremely cold environments found on planets, moons, or in deep space. RTGs convert heat generated from the radioactive decay of plutonium-238 into electricity using a themocouple, Plutonium-238 has proven to be an excellent heat source far deep space missions because of its high thermal power density, useful lifetime, minimal shielding requirements, and oxide stability.