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Enhanced Sulfate Management in HLW Glass Formulations

Technical Report ·
DOI:https://doi.org/10.2172/1059436· OSTI ID:1059436
 [1];  [1];  [1];  [1];  [2];  [3]
  1. The Catholic Univ. of America, Washington, DC (United States)
  2. EnergySolutions, Federal EPC, Inc., Columbia, MD (United States)
  3. USDOE Office of River Protection (ORP), Richland, WA (United States)
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The present report describes a series of small-scale crucible tests to determine sulfate solubility in HLW glasses, tests to assess the effect of compositional changes on sulfate solubility, and small-scale meIter tests to determine maximum acceptable sulfate loadings in HLW feeds to the meIter. The work was performed in accordance with the Test Plan for this work and the ORP contract. Glasses produced in previous melter tests using WTP and ORP waste and glass compositions were tested in the present work to determine sulfur solubility. In parallel, a glass formulation was developed for a previously untested HLW composition with one of the highest projected sulfate concentrations; that formulation was subsequently processed on the DM10 melter system at successively higher waste loadings to determine the maximum waste loading. Tests were also conducted on the DM10 on several HLW formulations which had been previously subjected to crucible-scale sulfur solubility testing; these formulations were selected based on sulfur solubility information for HLW glasses that was compiled in a previous report to WTP; similar information for LAW glasses was compiled in a report to ORP.
Research Organization:
Hanford Site (HNF), Richland, WA (United States); USDOE Office of River Protection (ORP), Richland, WA (United States)
Sponsoring Organization:
USDOE Office of Environmental Management (EM)
DOE Contract Number:
AC27-08RV14800
OSTI ID:
1059436
Report Number(s):
ORP--53932-REV0; VSL-12R2540-1, Rev 0
Country of Publication:
United States
Language:
English

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Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES