Static leach tests have been performed at glass surface area/leachant volume (SA/V) ratios of 10, 340, 2,000, and 20,000 m[sup [minus]1] to assess the effects of the SA/V on the mechanism and rate of the glass reaction. Tests were performed using actinide-doped borosilicate waste glasses [Savannah River Laboratory (SRL) 131 and SRL 202] to monitor the distribution of released radionuclides in tests at different SA/V. Solution results show the major effect of the SA/V to be dilution of reaction of products. Differences in the pH and silicic acid concentrations attained in tests at different SA/V then affect the reaction rate. Tests at low SA/V maintain leachate pH values similar to the initial leachant, while tests at higher SA/V result in higher leachate pH values being attained due to ion-exchange reactions. Transuranics released as the glass corrodes may exist in the leachate in concentrations far above their solubility limits by sorbing onto colloids, although the colloids may eventually settle out of solution. Transuranics also sorb onto the steel reaction vessel. The glass reaction progress can be characterized by three stages: (a) an initial stage where the reaction rate depends on the leachant pH, (b) an intermediate stage where the reaction slowsmore » toward a minimum rate as the leachate solution approaches saturation,'' and (c) a long-term stage where the reaction rate may be affected by the formation of secondary phases that control the solution chemistry. Tests at different SA/V cannot always be compared directly because the dominant reaction step and the observed reaction stage (initial, intermediate, or long-term) may not be the same.« less

A comparison of glass reaction at high and low glass surface/solution volume

The leaching behavior of borate waste glass SL-1

Detecting low levels of transuranics with electron energy loss spectroscopy

This review covers the corrosion interactions between different materials that are relevant to the disposal of high-level nuclear waste, in particular the waste forms and containers. The materials of interest are borosilicate glass, crystalline ceramics, metal alloys, and any corrosion products that might form. The available data show that these interactions depend on the structure, chemistry, thermodynamic history, and proximity of the materials in contact, as well as the environmental attributes, such as temperature, solution chemistry, and radiation. Several key mechanisms that govern these interactions are highlighted. Scientific gaps and open questions are summarized and discussed.

/pdf/review-of-corrosion-interactions-between-different-materials-4pyksn2fup.pdf

Review of corrosion interactions between different materials relevant to disposal of high-level nuclear waste

We have characterized the corrosion behavior of several Defense Waste Processing Facility (DWPF) reference waste glasses by conducting static dissolution tests with crushed glasses Glass dissolution rates were calculated from measured B concentrations in tests conducted for up to five years The dissolution rates of all glasses increased significantly after certain alteration phases precipitated Calculation of the dissolution rates was complicated by the decrease in the available surface area as the glass dissolves We took the loss of surface area into account by modeling the particles to be spheres, then extracting from the short-term test results the dissolution rate corresponding to a linear decrease in the radius of spherical particles The measured extent of dissolution in tests conducted for longer times was less than predicted with this linear dissolution model This indicates that advanced stages of corrosion are affected by another process besides dissolution, which we believe to be associated with a decrease in the precipitation rate of the alteration phases These results show that the dissolution rate measured soon after the formation of certain alteration phases provides an upper limit for the long-term dissolution rate, and can be used to determine a bounding value for the source term for radionuclide release from waste glasses The long-term dissolution rates measured in tests at 20,000 per m at 90 {degrees}C in tuff groundwater at pH values near 12 for the Environmental Assessment glass and glasses made with SRL 131 and SRL 202 frits, respectively

/pdf/dissolution-rates-of-dwpf-glasses-from-long-term-pct-57n1crbkry.pdf

Dissolution rates of DWPF glasses from long-term PCT

A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site.

/pdf/anl-technical-support-program-for-doe-environmental-hmvdjpx6av.pdf

ANL Technical Support Program for DOE Environmental Restoration and Waste Management

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ANL Technical Support Program for DOE Environmental Restoration and Waste Management