Salt splitting of sodium-dominated radioactive waste using ceramic membranes [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 1994. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 6 pages : digital, PDF file
- Additional Creators:
- Pacific Northwest Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- The potential for salt splitting of sodium dominated radioactive wastes by use of a ceramic membrane is reviewed. The technical basis for considering this processing technology is derived from the technology developed for battery and chlor-alkali chemical industry. Specific comparisons are made with the commercial organic membranes which are the standard in nonradioactive salt splitting. Two features of ceramic membranes are expected to be especially attractive: high tolerance to gamma irradiation and high selectivity between sodium and other ions. The objective of the salt splitting process is to separate nonradioactive sodium from contaminated sodium salts prior to other pretreatment processes in order to: (1) concentrate the waste in order to reduce the volume of subsequent additives and capacity of equipment, (2) decrease the pH of the waste in preparation for further processing, and (3) provide sodium with very low radioactivity levels for caustic washing of sludge or low level and mixed waste vitrification.
- Published through SciTech Connect., 08/01/1994., "pnl-sa--23723", " conf-940815--103", "DE95004578", "", SPECTRUM `94: international nuclear and hazardous waste management conference,Atlanta, GA (United States),14-18 Aug 1994., and Carlson, C.D.; Virkar, A.; Hollenberg, G.W.; Joshi, A.
- Funding Information:
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