Solidification of ion exchange resin wastes in hydraulic cement [electronic resource].
- Upton, N.Y. : Brookhaven National Laboratory, 1982. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 11 : digital, PDF file
- Additional Creators:
- Brookhaven National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
- Work has been conducted to investigate the solidification of ion exchange resin wastes with portland cements. These efforts have been directed toward the development of acceptable formulations for the solidification of ion exchange resin wastes and the characterization of the resultant waste forms. This paper describes formulation development work and defines acceptable formulations in terms of ternary phase compositional diagrams. The effects of cement type, resin type, resin loading, waste/cement ratio and water/cement ratio are described. The leachability of unsolidified and solidified resin waste forms and its relationship to full-scale waste form behavior is discussed. Gamma irradiation was found to improve waste form integrity, apparently as a result of increased resin crosslinking. Modifications to improve waste form integrity are described. 3 tables.
- Published through SciTech Connect., 01/01/1982., "bnl-31592", " conf-820424-32", "DE82018064", ANS topical meeting on treatment and handling of radioactive wastes, Richland, WA, USA, 19 Apr 1982., and Kalb, P.; Colombo, P.; Fuhrmann, M.; Neilson, R.M. Jr.
- Funding Information:
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