- Effect of Glass Composition on Activation Energy of Viscocity in Glass-Melting Temperature Range
- Published in the Journal of Non-Crystalline Solids
- Mathematical Modeling of Cold Cap
- Journal of Nuclear Materials, 429, (2012), 245-256
- High Waste Loading Glass Formulation For Hanford High-Aluminum High-Level Waste Streams (view presentation)
- Waste Load Enhancements For Hanford Low-Activity Waste Glasses (view presentation)
- ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management
- Empirical Model For Formulation of Crystal-Tolerant HLW Glasses
- Accepted for Publication 2012 in Ceramic Transactions
- Melting of Glass Batch: Model for Multiple Overlapping Gas-Evolving Reactions
- Thermochimica Acta 541 (2012) 8-14
- Thermochimica Acta 541 (2012) 8-14
- Effect of Alumina Source on the Rate of Melting Demonstrated with Nuclear Waste Glass Match
- International journal of Applied Glass Science 3 [1] 59-68 (2012)
- Thermal Analysis of Waste Glass Melter Feeds (view presentation)
- Effect of Glass Composition on Activation Energy of Viscosity in Glass-Melting-Temperature Range
- Presented at the 8th International Symposium on Radiation Safety Management
- Nuclear Waste Vitrification Efficency: Cold Cap Reactions
- Nuclear Waste Vitrification Efficiency: Cold Cap Reactions (view presentation)
- The 19th University Conference on Glass Science: Glasses for Energy 2-5 August 2011
- Crystallization During Processing of Nuclear Waste Glass
- Journal of Non-Crystalline Solids
- Effect of Glass-Batch Makeup on the Melting Process
- Published in Ceramics – Silikáty 54 (3) 193-211 (2010)
- Thermal Analysis of Waste Glass Batches: Effect of Batch Makeup on Gas-Evolving Reactions
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Published in J. Šesták and P. Šimon (Editors), Glassy, amorphous and nano-crystalline materials II. Reaction kinetics, thermodynamics and thermal analysis, Springer
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- Mathematical Modeling of Conversion Kinetics during Vitrification of Nuclear Waste
- Korean Nuclear Society Spring Meeting
- Iron-Phosphate Glass for Immobilization of Radioactive Technetium (view presentation)
- Waste Management 2012
- Rhenium Solubility in Borosilicate Nuclear Waste Glass: Implications for the Processing and Immobilization of Technetium-99
- Submitted for Publication in the Journal of Materials Chemistry of the Royal Chemistry Society
- Submitted for Publication in the Journal of Materials Chemistry of the Royal Chemistry Society
- Crystal-tolerant Glass Approach for Mitigation of Crystal Accumulation in Continuous Melters Processing Radioactive Waste
- Submitted for publication in the Journal of the American Ceramic Society
