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The Savannah River National Laboratory (SRNL) is part of a consortium that is looking to improve the retention of aluminum, chromium, and sulfate in high level radioactive waste (HLW) glass. Such glass has been produced by the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) in South Carolina since it began operating in 1996 and is planned to be produced by the River Protection Project-Waste Treatment Plant (WTP) at the Hanford Site in Washington. The consortium conducting this study, which is designated as Task No.6 by the Department of Energy (DOE) Environmental Management (EM) program sponsoring this effort, is made up of personnel from SRNL, the Pacific Northwest National Laboratory (PNNL), and the V.G. Khlopin Radium Institute (KRI). Coordinated glass experimental work will be performed by each member of the consortium. The glasses that are being studied were selected to further the understanding of composition-property relationships within the glass regions of interest to both DWPF and WTP. Forty-five (45) glasses, making up the US test matrix, were batched and fabricated to support the study. The chemical compositions of these glasses were measured by SRNL's Process Science Analytical Laboratory (PSAL) under the auspices of an analytical plan. In addition, two heat treatments (quenched and centerline canister cooled, ccc) of each glass were subjected to the 7-day Product Consistency Test (PCT) to assess their durabilities. More specifically, the Method A of the PCT (ASTM C-1285-2002) was used for these tests. Measurements of the resulting leachate solutions were conducted by PSAL under the auspices of three analytical plans. A statistical review of the PSAL measurements of the chemical compositions and of the PCT results for the glasses making up the US test matrix is provided in this memorandum. Target, measured, and measured bias-corrected compositional views were determined for these glasses. The durability results for the US study glasses are compared to those of the Environmental Assessment (EA) glass. All of the US glasses yielded PCTs that are lower than those of the EA glass. The largest PCT values are those measured for the ccc versions of US-27 and US-18 whose boron normalized leachate (NL[B]) values in grams per liter (g/L) were 16.4 g/L (based on the targeted composition) and 10.7 g/L (based on the targeted composition), respectively. The 16.4 g/L is just below the value of 16.695 g/L for EA's NL[B] that was reported by Jantzen et al. in WSRC-TR-92-0346, Revision 1. For the quenched version of the glasses, the largest NL[B] value is 0.67 g/L (based on the targeted composition). Thus, some statistically significant differences were seen between the quenched and ccc versions for some of the glasses. It should be noted that the thirty (30) glasses making up the KRI test matrix were not included in these analyses

A STATISTICAL REVIEW OF THE CHEMICAL COMPOSITION MEASUREMENTS AND PCT RESULTS FOR THE GLASSES FABRICATED AS PART OF THE US TEST MATRIX