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Meeting Materials Science & Technology 2019
Symposium Materials Issues in Nuclear Waste Management
Presentation Title Modeling of Carbonation Effects in a Cementitious Waste Form under Dry Environmental Conditions
Author(s) Peng Zhang, Zhiliang Chen, Andrew C. Garrabrants, Kevin G. Brown, J.C.L. Meeussen, Hans van der Sloot, David S. Kosson
On-Site Speaker (Planned) Peng Zhang
Abstract Scope Cast Stone is a cementitious wasteform for low-activity waste that is an option for near-surface disposal in an arid environment. Under aging conditions, gaseous CO2 can react with the material and alter its chemical/physical properties, thus altering the leaching characteristics of radionuclides and other constituents. Arid environment also can draw moisture during aging. The drying process affects the penetration rate of CO2 and the extent of reactions in the wasteform. However, this effect has not been considered in modeling long-term wasteform performance. A carbonation model is developed for the Cast Stone under dry environmental conditions. The LeachXS™/ORCHESTRA geochemical/reactive transport model is used to model the moisture transport, CO2 diffusion, and the resulting reactions. The carbonation rate as functions of environmental humidity and aging time are predicted and compared with experimental results. The simulation reveals correlation between drying and carbonation and provides a foundation for improved performance assessment of the wasteform.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Aerogels with Enhanced Gas Permeability and Mechanical Strength for use as Membranes in Radioiodine Capture
Dechlorination Methods and Ceramic Waste Forms for the Immobilization of Electrorefiner Salt
Disorder and Mass Transport in Model Waste Forms
Effect of Solution Chemistry on the Release Mechanism of Iodine from Iodoapatite Waste Form in Aqueous Environments
Electrical Properties of Nuclear Glasses
Energetics and Structure of Uranium-incorporated Iron Oxides
Impact of Redox on Crystallization Behavior of Spinel Crystals in HLW Borosilicate Glasses
Investigations into Physical and Chemical Characteristics of Nuclear Waste Glass Alteration Layers
Melt-Cast Ceramic Waste Forms: Laboratory Development and Scaled Demonstrations
Modeling of Carbonation Effects in a Cementitious Waste Form under Dry Environmental Conditions
Observations of Crystal Settling Behavior in a Full-Scale HLW Melter Mock-Up
Optimization of Frit Composition for Coupled Operation of the Defense Waste Processing Facility and Salt Waste Processing Facility at the Savannah River Site
P3-69: Corrosion Test Method Evaluation for Iodine Waste Forms
P3-70: Glass Pool Flow in a Joule-Heated, Laboratory-Scale Melter
P3-71: Multi-scale Structural Response of Pyrochlore Oxides to Swift Heavy Ion Irradiation
Predicting the Density of High-Level Waste Glass Compositions
The Influence of Reducing Conditions on the Stabilization of Iodine Containing Solid Secondary Wastes
The Relationship between Zeolite Type and Glass Dissolution Rate Resumption
Thermodynamics of Zeolite Precipitation in Stage III Glass Corrosion

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