Demonstration of sulfur solubility determinations in high waste loading, low-activity waste glasses
A method recommended by Pacific Northwest National Laboratory (PNNL) for sulfate solubility determinations in simulated low-activity waste glasses was demonstrated using three compositions from a recent Hanford high waste loading glass study. Sodium and sulfate concentrations in the glasses increased after each re-melting step. Visual observations of the glasses during the re-melting process reflected the changes in composition. The measured compositions showed that the glasses met the targeted values. The amount of SO3 retained in the glasses after washing was relatively high, ranging from 1.6 to 2.6 weight percent (wt %). Measured SnO2 concentrations were notably low in all of the study glasses. The composition of the wash solutions should be measured in future work to determine whether SnO2 is present with the excess sulfate washed from the glass. Increases in batch size and the amount of sodium sulfate added did not have a measureable impact on the amount of sulfate retained in the glass, although this was tested for only a single glass composition. A batch size of 250 g and a sodium sulfate addition targeting 7 wt %, as recommended by PNNL, will be used in future experiments.
- Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Org:
- Country of Publication:
- United States
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; SODIUM SULFATES; GLASS; TIN OXIDES; SULFUR; LOW-LEVEL RADIOACTIVE WASTES; CONCENTRATION RATIO; SODIUM; SOLUTIONS; MELTING; SOLUBILITY; ABUNDANCE; WASHING; SIMULATION; CHEMICAL COMPOSITION
Enter terms in the toolbar above to search the full text of this document for pages containing specific keywords.