Multibarrier Storage of Savannah River Plant Waste
The Savannah River Plant (SRP), operated by Du Pont for the U.S. Department of Energy, has produced nuclear materials for national defense programs since 1953. Acidic waste from the fuel reprocessing facilities on the plant site are neutralized and made alkaline for storage in large carbon steel tanks. Most fission products and waste actinides along with large amounts of nonradioactive waste (Fe, Mn, Al, etc.) precipitate from the alkaline solution to form an insoluble sludge on the bottom of the waste tanks. Supernatant liquid is evaporated to form salt cake and residual liquor that are also stored in the waste tanks. About 20 million gallons of waste are now stored at SRP. To provide for long term management of this waste, a conceptual process for incorporating waste in borosilicate glass is being developed at the Savannah River Laboratory. Solidified waste will be shipped to a federal repository.
KeywordsWaste Form Waste Glass Backfill Material Leach Rate Waste Package
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- 2.P. K. Baumgarten, D. Whitehurst, R. M. Wallace and J. M. Steed, “Development of an Ion Exchange Process for Removing 137Cs From High Level Radioactive Waste,” These Proceedings.Google Scholar
- 3.J. A. Kelley, “Evaluation of Glass as a Matrix for Solidification of Savannah River Waste, Nonradioactive and Tracer Studies,” USDOE Report DP-1382, E. I. du Pont de Nemours & Company, Inc., Savannah River Laboratory, Aiken, SC(1975).Google Scholar
- 4.J. A. Kelley, “Evaluation of Glass as a Matrix for Solidification of Savannah River Plant Waste, Radioactive Studies,” USDOE Report DP-1397, E. I. du Pont de Nemours & Company, Inc., Savannah River Laboratory, Aiken, SC(1975).Google Scholar
- 5.M. J. Plodinec, “Development of Glass Compositions for Immobilization of Savannah River Plant Wastes,” Scientific Basis for Nuclear Waste Management 1, 31 ( G. J. McCarthy, ed., Plenum Press, New York and London, 1979 ).Google Scholar
- 6.J. R. Wiley, “Leach Rates of High Activity Waste from Borosilicate Glass,” Nucl. Tech. 43, (1979).Google Scholar
- 7.J. R. Wiley, “Long Term Leach Rates of Actual Waste Glasses,” International Symposium on Ceramics in Nuclear Waste Management, American Ceramic Society, Nuclear Division, April 30-May 2, Cincinnati, Ohio(1979).Google Scholar
- 8.W. N. Rankin and J. A. Kelley, “Microstructure and Leachability of Vitrified Radioactive Wastes,” Nucl. Tech. 41, (1978).Google Scholar
- 9.M. H. Tennant, “Temperature Generated by Underground Storage of Defense Waste Canisters,” These proceedings.Google Scholar
- 10.Composition provided by M. A. Molecke, Sandia Laboratories, Albuquerque, NM.Google Scholar
- 11.Composition provided by R. W. Potter, USGS, Menlo Park, CA.Google Scholar
- 12.W. N. Rankin, “Canister Compatibility with Carlsbad Salt,” International Symposium on the Scientific Basis for Nuclear Waste Management, Boston, MA, Nov. 26–291(1979).Google Scholar