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Chemical Composition and PCT Data for the Initial Set of Hanford Enhanced Waste Loading Glasses.

DE141133390

Publication Date	2014
Personal Author	Fox, K. M.; Edwards, T. B.
Page Count	168
Abstract	In this report, the Savannah River National Laboratory provides chemical analyses and Product Consistency Test results for 20 simulated high level waste glasses fabricated by the Pacific Northwest National Laboratory. The results of these analyses will be used as part of efforts to revise or extend the validation ranges of the current Hanford Waste Treatment and Immobilization Plant glass property models to cover a broader span of waste compositions. The measured chemical composition data are reported and compared with the targeted values for each component for each glass. Two components of the study glasses, fluorine and silver, were not measured since each of these species would have required the use of an additional preparation method and their measured values were likely to be near or below analytical detection limits. Some of the glasses were difficult to prepare for chemical analysis. A sodium peroxide fusion dissolution method was successful in completely dissolving the glasses. Components present in the glasses in minor concentrations can be difficult to measure using this dissolution method due to dilution requirements. The use of a lithium metaborate preparation method for the minor components (planned for use since it is typically successful in digesting Defense Waste Processing Facility HLW glasses) resulted in an unacceptable amount of undissolved solids remaining in the sample solutions. An acid dissolution method was used instead, which provided more thorough dissolution of the glasses, although a small amount of undissolved material remained for some of the study glasses. The undissolved material was analyzed to determine those components of the glasses that did not fully dissolve. These components (e.g., calcium and chromium) were present in sufficient quantities to be reported from the measurements resulting from the sodium peroxide fusion preparation method, which did not leave undissolved material. Overall, the analyses resulted in sums of oxides that ranged from about 98 to 101.5 wt % for the study glasses, indicating excellent recovery of all the components in the chemical composition analyses.
Keywords	Radioactive waste processing Glass Chemical composition Detection Dissolution Fabrication Hanford Reservation High level radioactive wastes Waste treatment
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77G - Radioactive Wastes & Radioactivity
Corporate Authors	Savannah River National Lab., Aiken, SC.
Document Type	Technical Report
NTIS Issue Number	201425
Contract Number	DE-AC09-08SR22470

Chemical Composition and PCT Data for the Initial Set of Hanford Enhanced Waste Loading Glasses.

Chemical Composition and PCT Data for the Initial Set of Hanford Enhanced Waste Loading Glasses.
DE141133390

Publication Date	2014
Personal Author	Fox, K. M.; Edwards, T. B.
Page Count	168
Abstract	In this report, the Savannah River National Laboratory provides chemical analyses and Product Consistency Test results for 20 simulated high level waste glasses fabricated by the Pacific Northwest National Laboratory. The results of these analyses will be used as part of efforts to revise or extend the validation ranges of the current Hanford Waste Treatment and Immobilization Plant glass property models to cover a broader span of waste compositions. The measured chemical composition data are reported and compared with the targeted values for each component for each glass. Two components of the study glasses, fluorine and silver, were not measured since each of these species would have required the use of an additional preparation method and their measured values were likely to be near or below analytical detection limits. Some of the glasses were difficult to prepare for chemical analysis. A sodium peroxide fusion dissolution method was successful in completely dissolving the glasses. Components present in the glasses in minor concentrations can be difficult to measure using this dissolution method due to dilution requirements. The use of a lithium metaborate preparation method for the minor components (planned for use since it is typically successful in digesting Defense Waste Processing Facility HLW glasses) resulted in an unacceptable amount of undissolved solids remaining in the sample solutions. An acid dissolution method was used instead, which provided more thorough dissolution of the glasses, although a small amount of undissolved material remained for some of the study glasses. The undissolved material was analyzed to determine those components of the glasses that did not fully dissolve. These components (e.g., calcium and chromium) were present in sufficient quantities to be reported from the measurements resulting from the sodium peroxide fusion preparation method, which did not leave undissolved material. Overall, the analyses resulted in sums of oxides that ranged from about 98 to 101.5 wt % for the study glasses, indicating excellent recovery of all the components in the chemical composition analyses.
Keywords	Radioactive waste processing Glass Chemical composition Detection Dissolution Fabrication Hanford Reservation High level radioactive wastes Waste treatment
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77G - Radioactive Wastes & Radioactivity
Corporate Authors	Savannah River National Lab., Aiken, SC.
Document Type	Technical Report
NTIS Issue Number	201425
Contract Number	DE-AC09-08SR22470