Waste Form Release Calculations for the 2001 Immobilized Low-Activity Waste Performance Assessment

Bacon, Diana H.; McGrail, B. Peter

doi:10.2172/781070

Cited by 22 publications

(23 citation statements)

References 21 publications

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“…From knowledge of the controlling release mechanisms, one can build either mechanistic (physicochemical) or empirical algorithms that are needed by PA computer codes to generate long-term predictions on the fate of potential contaminants in the waste forms. Examples of the types of mechanistic and empirical algorithms and overall PA process are found in Bacon et al (2000), Bacon and McGrail et al (2001), McGrail et al (2001) and Mann et al (2001).…”

Section: Waste Form Leach Testing-pa Supportmentioning

confidence: 99%

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Supplemental Immobilization Cast Stone Technology Development and Waste Form Qualification Testing Plan

Westsik

Serne

Pierce

et al. 2013

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iii SummaryThe Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). The pretreatment facility will have the capacity to separate all of the tank wastes into the HLW and LAW fractions, and the HLW Vitrification Facility will have the capacity to vitrify all of the HLW. However, a second immobilization facility will be needed for the expected volume of LAW requiring immobilization. A number of alternatives, including Cast Stone-a cementitious waste form-are being considered to provide the additional LAW immobilization capacity.The supplemental immobilization waste form must be acceptable for disposal in the IDF. This supplemental immobilization waste form testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements.Specifications for the supplemental immobilization waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF portion of the Hanford Facility Resource and Recovery Act (RCRA) Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product.

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Section: Waste Form Leach Testing-pa Supportmentioning

confidence: 99%

“…Therefore, under DOE Order 414.1D (DOE 2011), STORM cannot be used for future risk and PA analyses. More details on STORM can be found in Bacon et al (2000Bacon et al ( , 2004, Bacon and McGrail (2001), McGrail et al (2001), and Mann et al (2001Mann et al ( , 2003.…”

Section: Reactive Transport Simulators For the Waste Form Calculationsmentioning

confidence: 99%

Supplemental Immobilization Cast Stone Technology Development and Waste Form Qualification Testing Plan

Westsik

Serne

Pierce

et al. 2013

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“…A general rate equation has been formulated that describes the dissolution of glass as a function of a number of these different parameters (e.g., the amount of moisture, amount of silicic acid, pH, amount of secondary phases) . The normalized flux to the vadose zone for radionuclides released from the waste packages for the 2001 ILAW performance assessment that incorporates this dissolution concept has recently been described (Bacon and McGrail 2001).…”

Section: Release From Immobilized Low Activity Waste (Ilaw)mentioning

confidence: 99%

“…A general rate equation was formulated that describes the dissolution of glass as a function of key parameters (e.g., pH). This rate equation was subsequently reflected within an equation that expressed the normalized flux of radionuclides to the vadose zone for glass waste packages (Bacon McGrail 2001). The third configuration is considerably more advanced and representative of contaminant release from glass than the other two configurations.…”

Section: Glass Modelmentioning

confidence: 99%

Data Catalog for Models Simulating Release of Contaminants from Hanford Site Waste Sources

Riley

Lopresti²

2001

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ForewordThe Characterization of Systems (CoS) Task under the Groundwater/Vadose Zone Integration Project is responsible for establishing a consistent set of data, parameters, and conceptual models to support efforts at the Hanford Site to estimate contaminant migration and impacts. As part of these efforts CoS is assembling a series of catalogs to identify the depth and breadth of existing data and to facilitate access to those data. The preparation of these catalogs is aimed at facilitating the development of comprehensive, useable, and scientifically defensible database(s). However, it is also envisioned that these catalogs will be "living documents" that will continue to evolve as other existing data is found and new data collected.This catalog summarizes information on models that have been used to simulate release of chemical and radioactive contaminants from waste sources on the Hanford Site over the past 14 years. v Summary Models have been used to simulate the transport and fate of contaminants at the Hanford Site to assess the effectiveness of various environmental restoration and waste management activities and to estimate impacts to environmental and human receptors. Part of the process includes the ability to simulate the release to the vadose zone and groundwater of a wide range of contaminants from a wide range of waste sources that have been generated at the Hanford Site as a result of over 40 years of defense production activities.Mathematical formulas that express the release of contaminants from various waste sources and their application in past assessments are documented in many reports published over the past 14 years. The sheer number of reports in which such information is reported makes it difficult for individuals to access this information in a timely manner. To provide users carrying out Hanford assessments with improved access to the information and data on release model capability, researchers at the Pacific Northwest National Laboratory (PNNL) consolidated these sources of information and data into a single location. This work was conducted under the Vadose Zone Groundwater Integration Project managed by Bechtel Hanford Incorporated for the U.S. Department of Energy -Richland Operations (DOE-RL).This report provides summaries of release models used in Hanford Site assessments published over the past 14 years (1987 to 2001). Mathematical formulations that commonly have been used in recent years (i.e., salt-cake, cement, soil-debris, reactor block, glass, and corrosion) are described, along with associated parameter definitions and their units. Tables in this report provide links to data sources needed to implement the models. These links enable users to quickly locate the specific release model information and data sources they need for applying the models to future to site assessments.During the compilation of the catalog, the authors became aware of significant differences in the level of complexity of release models applied over the years to meet Hanford Site assessment objectives...

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“…To estimate the waste form release rates for these PAs, Pacific Northwest National Laboratory (PNNL) has contributed waste form release simulations (Chen et al 1997;Bacon and McGrail 1998;Bacon and McGrail 2001;Bacon et al 2002;Bacon and McGrail 2003;Bacon and McGrail 2005) that are based on data packages quantifying dissolution rates of waste package materials, including ILAW and BV glasses (Mann et al 2001;Pierce et al 2004a;Pierce et al 2004b). The waste form release simulations are performed with the Subsurface Transport Over Reactive Multiphases (STORM) code (Bacon et al 2004).…”

Section: Introductionmentioning

confidence: 99%

Corrosion of Metal Inclusions In Bulk Vitrification Waste Packages

Bacon¹,

Pierce²,

Wellman³

et al. 2006

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SummaryThe primary purpose of the work reported here is to analyze the potential effect of the release of technetium (Tc) from metal inclusions in bulk vitrification (BV) waste packages once they are placed in the Integrated Disposal Facility (IDF). As part of the strategy for immobilizing waste from the underground tanks at Hanford, selected wastes will be immobilized using BV. During analyses of the glass produced in engineering-scale tests, metal inclusions were found in the glass product. This report contains the results from experiments designed to quantify the corrosion rates of metal inclusions found in the glass product from Test ES-32B (AMEC 2005) and simulations designed to compare the rate of Tc release from the metal inclusions to the release of Tc from glass produced with the BV process. Due to the probability of oxidizing conditions surrounding the waste packages in the IDF, in the simulations the Tc in the metal inclusions and the glass is conservatively assumed to be released congruently as soluble TcO 4 -. The experimental results and modeling calculations (Bacon and McGrail 2005) show that the metal corrosion rate will, under all conceivable conditions at the IDF, be dominated by the presence of the passivating layer and corrosion products on the metal particles. As a result, the release of Tc from the metal particles at the surfaces of fractures in the glass releases at a rate similar to the Tc present as a soluble salt (McGrail et al. 2003;Pierce et al. 2005). The release of the remaining Tc in the metal is controlled by the dissolution of the glass matrix.The dissolution kinetics of iron [Fe(0)] was quantified under conditions of constant dissolved O 2 [O 2 (aq)] and in solutions that minimized the formation of a passive film on the metal surface. These tests were performed to determine the forward reaction rate for the metal inclusions in the BV glass. Single-pass flow through (SPFT) tests were conducted over the pH(23°C) range from 7.0 to 12.0 and temperature range from 23°C to 90°C. The presence of EDTA minimized the formation of a passive film and Fe-bearing secondary phase(s) during testing allowing us to determine the forward dissolution rate. These results indicate that the corrosion of Fe(0) is relatively insensitive to pH and temperature and the forward rate is 3 to 4 orders of magnitude higher than when a passive film and corrosion products are present. Tests conducted with Amasteel (a low carbon steel non-radioactive surrogate) and ES-32B metal indicated that the forward dissolution rates for both metals were similar, if not identical. In other words, the presence of P and 99 Tc in the ES-32B metal appeared to have little effect on the forward dissolution rate. These results indicate that the corrosion rate of the ES-32B metal at repository relevant conditions was not significantly less than the surrogate metal. Because the effects of temperature (E a = 15 ±5 kJ/mol at pH(23°C) = 9.0 based on Fe release from ES-32B metal) and solution pH (η = -0.13 ±0.02 at 70°C based on Fe releas...

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Waste Form Release Calculations for the 2001 Immobilized Low-Activity Waste Performance Assessment

Cited by 22 publications

References 21 publications

Supplemental Immobilization Cast Stone Technology Development and Waste Form Qualification Testing Plan

Supplemental Immobilization Cast Stone Technology Development and Waste Form Qualification Testing Plan

Data Catalog for Models Simulating Release of Contaminants from Hanford Site Waste Sources

Corrosion of Metal Inclusions In Bulk Vitrification Waste Packages

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