Final Report - LAW Envelope C Glass Formulation Testing to Increase Waste Loading, VSL-05R5900-1

Kruger, Albert A.; Pegg, Ian L.; Matlack, Keith S.; Joseph, Innocent; Muller, Isabelle S.; Gong, William C.

doi:10.2172/1109496

Cited by 6 publications

(5 citation statements)

References 4 publications

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“…Figure a, which represents a Na 2 O–B 2 O 3 –SiO 2 molar ternary phase diagram, compares the compositions from the present study to ∼950 LAW ,,,,− and ∼50 HLW ,,− formulations of simulated nuclear waste glasses, wherein the complex oxide LAW and HLW glass compositions are normalized to these three components. It is evident that most LAW glasses are to the low B 2 O 3 side of the ternary, spanning across all of the four regions of the DYB classification (Figure ) with a majority of them located in region 4.…”

Section: Discussionmentioning

confidence: 99%

Correlating Sulfur Solubility with Short-to-Intermediate Range Ordering in the Structure of Borosilicate Glasses

Saini

Kapoor²,

Youngman

et al. 2022

J. Phys. Chem. C

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HAL is a multi-disciplinary open access archive for the deposit and dissemination of scientific research documents, whether they are published or not. The documents may come from teaching and research institutions in France or abroad, or from public or private research centers. L'archive ouverte pluridisciplinaire HAL, est destinée au dépôt et à la diffusion de documents scientifiques de niveau recherche, publiés ou non, émanant des établissements d'enseignement et de recherche français ou étrangers, des laboratoires publics ou privés.

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Section: Discussionmentioning

confidence: 99%

Correlating Sulfur Solubility with Short-to-Intermediate Range Ordering in the Structure of Borosilicate Glasses

Saini

Kapoor²,

Youngman

et al. 2022

J. Phys. Chem. C

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“…The data pertaining to SO 3 solubility in 1074 LAW and HLW glass compositions have been collected from 23 publications. ,,,,,− The majority of the data has been drawn from studies on sulfur tolerance in simulated LAW glasses; ,,,,− ,, and the remaining data have been extracted from the experimental studies on simulated HLW glasses. ,,− Sulfur solubility (in nuclear waste glasses), as extracted from literature and used in this study, corresponds to the limiting sulfate concentration in the glasses measured just before the formation (first appearance) of the salt layer on the surface of the glass/melt. ,,,, Here, it may be helpful to differentiate between two terms“solubility” and “retention.” The solubility is defined as the concentration of sulfur at an established equilibrium between dissolved and atmospheric sulfur (most likely in the form of oxides). However, the glassmaking process generally does not allow molten glass to reach equilibrium.…”

Section: Consolidation and Evaluation Of Databasementioning

confidence: 99%

“…The data pertaining to SO 3 solubility in 1074 LAW and HLW glass compositions have been collected from 23 publications. 2,3,6,9,17,25−42 The majority of the data has been drawn from studies on sulfur tolerance in simulated LAW glasses; 3,6,9,17,[25][26][27][28][29][30][31][32][33][34][35]37,42 and the remaining data have been extracted from the experimental studies on simulated HLW glasses. 2,31,38−41 Sulfur solubility (in nuclear waste glasses), as extracted from literature and used in this study, corresponds to the limiting sulfate concentration in the glasses measured just before the formation (first appearance) of the salt layer on the surface of the glass/melt.…”

Section: Consolidation and Evaluation Of Databasementioning

confidence: 99%

Machine Learning Enabled Models to Predict Sulfur Solubility in Nuclear Waste Glasses

Han

Huang

et al. 2021

ACS Appl. Mater. Interfaces

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The U.S. Department of Energy is considering implementing the direct feed approach for the vitrification of low-activity waste (LAW) and high-level waste (HLW) at the Hanford site in Washington state. If implemented, the nuclear waste with a higher concentration of alkali/alkaline-earth sulfates (than expected under the previously proposed vitrification scheme) will be sent to the vitrification facility. It will be difficult for the existing empirical models to predict sulfate solubility in these glasses or design glass formulations with enhanced sulfate loadings in such a scenario. Further, the existing models are unable to produce reliable predictions when applied to HLW glasses whose composition falls outside of the range encompassed by the database used to develop/calibrate the models. Accordingly, this study harnesses the power of artificial intelligence (machine learning, ML) with a goal to address the limitations of the existing models. Toward this, three ML models have been trained using a large database; comprising >1000 LAW and HLW glasses and encompassing a wide range of glass compositions and processing variables. Next, the ML model with the best prediction performance has been used to quantitatively assess and rank the influence (i.e., importance) of glasses’ compositional/processing variables on the SO3 solubility in the glasses. Finally, on the premise of such understanding of influential and inconsequential variables, two closed-form analytical modelswith disparate degrees of complexity (one highly parametrized and one with fewer input variables)have been developed. Results show that both analytical models produce predictions of SO3 solubility in LAW and HLW glasses with an accuracy analogous to ML models and substantially higher than the analytical models that represent the current state-of-the-art. Overall, this study’s outcomes present a roadmapinformed by data and channeled by artificial intelligencethat can be leveraged in the future to design nuclear waste glasses with unprecedented sulfur loadings.

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“…For commercial applications, the objective can be designing a new glass composition for a new product or modifying the existing composition for product improvement or process changes. Glass formulation is needed in various stages of waste vitrification technology development; for example, formulating a glass for a specific waste to demonstrate a new processing technology, 7-10) developing enhanced glass formulations for specific Hanford wastes, [11][12][13][14][15] or formulating a glass frit composition for each sludge batch to produce actual radioactive glass at the DWPF. 16,17) The last case also involves variability confirmation so that the selected composition can tolerate the uncertainties from various sources.…”

Section: Waste Glass Formulationmentioning

confidence: 99%

“…If the model uses the transformed property such as ln(η), that should be used as P in Eq. (12). The iterative approach focuses on key properties or constraints that are critical in determining the acceptance or processability of the final glass to the initial design set of glass compositions.…”

Section: Iterative Glass Formulationmentioning

confidence: 99%

Glass Property Models, Constraints, and Formulation Approaches for Vitrification of High-Level Nuclear Wastes at the US Hanford Site

Kim¹

2015

J. Korean Ceram. Soc

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Current plans for legacy nuclear wastes stored in underground tanks at the U.S. Department of Energy's Hanford Site in Washington are that they will be separated into high-level waste and low-activity waste fractions that will be vitrified separately. Formulating optimized glass compositions that maximize the waste loading in glass is critical for successful and economical treatment and immobilization of these nuclear wastes. Glass property-composition models have been developed and applied to formulate glass compositions for various objectives for the past several decades. Property models with associated uncertainties combined with composition and property constraints have been used to develop preliminary glass formulation algorithms designed for vitrification process control and waste-form qualification at the planned waste vitrification plant. This paper provides an overview of the current status of glass property-composition models, constraints applicable to Hanford waste vitrification, and glass formulation approaches that have been developed for vitrification of hazardous and highly radioactive wastes stored at the Hanford Site.

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Final Report - LAW Envelope C Glass Formulation Testing to Increase Waste Loading, VSL-05R5900-1

Cited by 6 publications

References 4 publications

Correlating Sulfur Solubility with Short-to-Intermediate Range Ordering in the Structure of Borosilicate Glasses

Correlating Sulfur Solubility with Short-to-Intermediate Range Ordering in the Structure of Borosilicate Glasses

Machine Learning Enabled Models to Predict Sulfur Solubility in Nuclear Waste Glasses

Glass Property Models, Constraints, and Formulation Approaches for Vitrification of High-Level Nuclear Wastes at the US Hanford Site

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