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Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate.

DE2005833182

Publication Date	2005
Personal Author	Moyer, B. A.; Bonnesen, P. V.; Brown, G. M.; Bryan, J. C.; Chambliss, C. K.; Haverlock, T. J.; Levitskaia, T. G.
Page Count	16
Abstract	The overall goal of this research conducted under the auspices of the USDOE Environmental Management Science Program (EMSP) is to provide a scientific foundation upon which the feasibility of new liquid-liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated. Disposal of high-level nuclear waste is horrendously expensive, in large part because the actual radioactive matter in the tanks has been diluted over 10,000-fold by ordinary inorganic chemicals. Quite simply, if the radioactive matter and bulk inorganic chemicals could be separated into separate streams, large cost savings would accrue, because the latter stream is much cheaper to dispose of. In principle, one could remove the radionuclides from the waste, leaving behind the bulk of the waste; or one could remove certain bulk chemicals from the waste, leaving behind the radionuclides. The preponderance of effort over the past two decades has focused on the former approach, which produces a high-level stream for vitrification and a low-activity stream for either vitrification (Hanford) or grout (Savannah River). At Hanford, a particular concern arises in that vitrification of a large volume of low-activity waste will be unacceptably expensive. To make matters worse, a projected future deficit of tank space may necessitate construction of expensive new tanks. These problems have raised questions as to whether a solution could be devised based on separation of sodium from the waste, resulting in the reduction of the total volume of waste that must be vitrified.
Keywords	Tanks Radioactive wastes Separation Sodium Chemistry Construction Grouting Solvent extraction Vitrification Management
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Oak Ridge National Lab., TN. Chemical and Analytical Sciences Div.; Department of Energy, Washington, DC.; University of North Texas, Denton. Dept. of Chemistry.
Supplemental Notes	Prepared in cooperation with University of North Texas, Denton. Dept. of Chemistry. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200524

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate.

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate.
DE2005833182

Publication Date	2005
Personal Author	Moyer, B. A.; Bonnesen, P. V.; Brown, G. M.; Bryan, J. C.; Chambliss, C. K.; Haverlock, T. J.; Levitskaia, T. G.
Page Count	16
Abstract	The overall goal of this research conducted under the auspices of the USDOE Environmental Management Science Program (EMSP) is to provide a scientific foundation upon which the feasibility of new liquid-liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated. Disposal of high-level nuclear waste is horrendously expensive, in large part because the actual radioactive matter in the tanks has been diluted over 10,000-fold by ordinary inorganic chemicals. Quite simply, if the radioactive matter and bulk inorganic chemicals could be separated into separate streams, large cost savings would accrue, because the latter stream is much cheaper to dispose of. In principle, one could remove the radionuclides from the waste, leaving behind the bulk of the waste; or one could remove certain bulk chemicals from the waste, leaving behind the radionuclides. The preponderance of effort over the past two decades has focused on the former approach, which produces a high-level stream for vitrification and a low-activity stream for either vitrification (Hanford) or grout (Savannah River). At Hanford, a particular concern arises in that vitrification of a large volume of low-activity waste will be unacceptably expensive. To make matters worse, a projected future deficit of tank space may necessitate construction of expensive new tanks. These problems have raised questions as to whether a solution could be devised based on separation of sodium from the waste, resulting in the reduction of the total volume of waste that must be vitrified.
Keywords	Tanks Radioactive wastes Separation Sodium Chemistry Construction Grouting Solvent extraction Vitrification Management
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Oak Ridge National Lab., TN. Chemical and Analytical Sciences Div.; Department of Energy, Washington, DC.; University of North Texas, Denton. Dept. of Chemistry.
Supplemental Notes	Prepared in cooperation with University of North Texas, Denton. Dept. of Chemistry. Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200524