Solvent extraction of radionuclides from aqueous tank waste

Conference · Tue Oct 01 00:00:00 EDT 1996

OSTI ID:375684

Bonnesen, P; Sachleben, R; Moyer, B ^[1]

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1. Oak Ridge National Lab., TN (United States)

The purpose of this task is to develop an efficient solvent-extraction and stripping process to remove the fission products {sup 99}Tc, {sup 90}Sr, and {sup 137}Cs from alkaline tank waste, such as those stored at Hanford and Oak Ridge. As such, this task expands on FY 1995`s successful development of a solvent-extraction and stripping process for technetium separation from alkaline tank-waste solutions. This process now includes the capability of removing both technetium and strontium simultaneously. In this form, the process has been named SRTALK and will be developed further in this program as a prelude to developing a system capable of removing technetium, strontium, and cesium.

• Research Organization: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• OSTI ID: 375684
• Report Number(s): PNNL-SA-27105; CONF-960158-; ON: DE96005494; TRN: 96:003739-0011
• Resource Relation: Conference: Efficient separations and processing crosscutting program 1996 technical meeting, Gaithersburg, MD (United States), 16-19 Jan 1996; Other Information: PBD: [1996]; Related Information: Is Part Of Efficient separations and processing crosscutting program 1996 technical exchange meeting. Proceedings; PB: 52 p.
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
HIGH-LEVEL RADIOACTIVE WASTES
RADIOACTIVE WASTE PROCESSING
UNDERGROUND STORAGE
TANKS
REMEDIAL ACTION
RADIOISOTOPES
SOLVENT EXTRACTION