54 research outputs found

    Vitrification of High-Level Waste at the Savannah River Site

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    ABSTRACT The objective of this study was to experimentally measure the properties and performance of a series of glasses with compositions that could represent high level waste Sludge Batch 5 (SB5) as vitrified at the Savannah River Site Defense Waste Processing Facility. These data were used to guide frit optimization efforts as the SB5 composition was finalized. Glass compositions for this study were developed by combining a series of SB5 composition projections with a group of candidate frits. The study glasses were fabricated using depleted uranium and their chemical compositions, crystalline contents and chemical durabilities were characterized. Trevorite was the only crystalline phase that was identified in a few of the study glasses after slow cooling, and is not of concern as spinels have been shown to have little impact on the durability of high level waste glasses. Chemical durability was quantified using the Product Consistency Test (PCT). All of the glasses had very acceptable durability performance. The results of this study indicate that a frit composition can be identified that will provide a processable and durable glass when combined with SB5

    EM-21 Higher Waste Loading Glasses for Enhanced DOE High-Level Waste Melter Throughput Studies -10194

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    ABSTRACT Supplemental validation data have been generated that will be used to determine the applicability of the current Defense Waste Processing Facility (DWPF) liquidus temperature (T L ) model to expanded DWPF glass regions of interest based on higher waste loadings. For those study glasses which had very close compositional overlap with the model development and/or model validation ranges (except TiO 2 and MgO concentrations), there was very little difference in the predicted and measured T L values, even though the TiO 2 contents were above the 2 wt% upper concentration covered by the model. The results indicate that the current T L model is applicable in these compositional regions. As the compositional overlap between the model validation ranges diverged from the target glass compositions, the T L data suggest that the model underpredicted the measured values. These discrepancies imply that the influence of individual oxides or their combinations at concentrations outside of the model development and/or previous validation regions may not be adequately assessed by the current model. These oxides include B 2 O 3 , SiO 2 , MnO, TiO 2 and/or their combinations. More data are required to fill in these anticipated DWPF compositional regions so that the model coefficients could be refit to account for these influences. INTRODUCTION High-level waste (HLW) throughput (i.e., the amount of waste processed per unit time) is a function of several parameters, two of which are extremely critical: waste loading (WL) and melt rate. For the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS), increasing HLW throughput would significantly reduce the overall mission life cycle costs for the Department of Energy (DOE)

    Control of Nepheline Crystallization in Nuclear Waste Glass

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    Abstract Glass frits with a high B 2 O 3 concentration have been designed which, when combined with high-alumina concentration nuclear waste streams, will form glasses with durabilities that are acceptable for repository disposal and predictable using a free energy of hydration model. Two glasses with nepheline discriminator values closest to 0.62 showed significant differences in normalized boron release between the quenched and heat treated versions of each glass. X-ray diffraction confirmed that nepheline crystallized in the glass with the lowest nepheline discriminator value, and nepheline may also exist in the second glass as small nanocrystals. The high-B 2 O 3 frit was successful in producing simulated waste glasses with no detectable nepheline crystallization at waste loadings of up to 45 wt%. The melt rate of this frit was also considerably better than other frits with increased concentrations of Na 2 O. Introduction High-level wastes, a legacy of Cold War production of nuclear materials for defense, are stored at several Department of Energy (DOE) facilities in the United States. These wastes, typically in the form of a sludge stored in underground tanks, are being vitrified with a glass frit or mined, glass-forming minerals to form a glass wasteform suitable for final disposal in the national repository. The waste glass must meet DOE requirements for durability, or resistance to chemical leaching in water at elevated temperatures, in order to be acceptable to the repository. A significant volume of these wastes has been identified as containing high concentrations of Al 2 O 3 and Na 2 O. Based on current blending and washing strategies, waste streams at the Savannah River Site (SRS) have been identified with Al 2 O 3 concentrations from 25 to 40 wt%. Concentrations in some wastes at Hanford are as high as 80 wt%. The combination of high Al 2 O 3 and Na 2 O concentrations in the waste, coupled with lower SiO 2 concentrations in the glass as waste loadings (WLs) increase, can lead to the crystallization of nepheline (NaAlSiO 4 ). The impact of crystallization, or devitrification, on the durability of the glass wasteform is dependent upon the type and extent of the crystalline phases that develop
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