Evaluation of stainless steel zirconium alloys as high-level nuclear waste forms

Crystallization sequence and microstructure evolution of Synroc samples crystallized from CaZrTi2O7 melts

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

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

A program was established for the DOE Office of Environmental 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. This report covers progress in FY 1995 on the following tasks: (1) Tests are ongoing to evaluate and compare the reactivity of fully radioactive glasses with that of glasses having the same compositions except for the absence of radionuclides under conditions representative of a high-level waste repository environment. Data from these tests will be used to evaluate the effect of radionuclides on the glass corrosion behavior and to determine the disposition of the radionuclides as the glass corrodes. Static dissolution tests and unsaturated tests are being conducted with several Defense Waste Processing Facility (DWPF) and West Valley Demonstration Project (WVDP) glasses. (2) A series of static dissolution tests is being performed to compare the corrosion behavior of nuclear waste glasses made with SRL 131 and SRL 202 frits at different S/V ratios. The S/V ratio affects the extent to which dissolved glass species are diluted; the solution chemistry then affects continued glass dissolution. The solutions generated in tests at high S/V ratios are conducive to the formation of alteration phases that may be deleterious to the glass. After long time periods, the glass dissolution rates of both glasses increase coincidentally with the formation of analcime and other alteration phases. However, the release of radionuclides from the glasses into solution is controlled by their individual solubilities.

/pdf/anl-technical-support-program-for-doe-office-of-jbprl2vm0a.pdf

ANL technical support program for DOE Office of Environmental Management. Annual report, October 1994--September 1995

Waste forms made of a glass-crystal composite (GCC) are being evaluated at Argonne National Laboratory for their potential use in the disposal of low-level nuclear and hazardous waste materials. This waste form is being developed within the framework strategy of DOE`s minimum Additive Waste Stabilization (MAWS) Program. The MAWS protocol involves the blending of multiple waste streams to achieve an optimal feed composition, which eliminates the need to use large amounts of additives to produce an acceptable waste form. The GCCs have a particularly useful utility in their ability to incorporate waste streams with high metal contents, including those that contain large amounts of scrap metals, and in their potential for sequestering radionuclide and hazardous constituents in corrosion-resistant mineral phases. This paper reports the results from tests conducted with simulated feeds representative of potential DOE and industry waste streams. Topics addressed include the partitioning of various radioactive and hazardous constituents between the glass and crystalline portions of the waste form, the development of secondary phases on the altered sample surfaces during corrosion testing, and the fate of waste components during corrosion testing, as indicated by elements released to solution and microanalysis of the reacted solid samples.

/pdf/an-evaluation-of-glass-crystal-composites-for-the-disposal-2goxy3tua2.pdf

An Evaluation of Glass-Crystal Composites For the Disposal of Nuclear and Hazardous Waste Materials

Corrosion of a Plutonium-Bearing Titanate Ceramic

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ANL Technical Support Program for DOE Environmental Restoration and Waste Management

ANL technical support program for DOE Office of Environmental Management. Annual report, October 1994--September 1995

An Evaluation of Glass-Crystal Composites For the Disposal of Nuclear and Hazardous Waste Materials

Corrosion of a Plutonium-Bearing Titanate Ceramic