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Title: FY2016 ILAW Glass Corrosion Testing with the Single-Pass Flow-Through Method

Abstract

The inventory of immobilized low-activity waste (ILAW) produced at the Hanford Tank Waste Treatment and Immobilization Plant (WTP) will be disposed of at the near-surface, on-site Integrated Disposal Facility (IDF). When groundwater comes into contact with the waste form, the glass will corrode and radionuclides will be released into the near-field environment. Because the release of the radionuclides is dependent on the dissolution rate of the glass, it is important that the performance assessment (PA) model accounts for the dissolution rate of the glass as a function of various chemical conditions. To accomplish this, an IDF PA model based on Transition State Theory (TST) can be employed. The model is able to account for changes in temperature, exposed surface area, and pH of the contacting solution as well as the effect of silicon concentrations in solution, specifically the activity of orthosilicic acid (H4SiO4), whose concentration is directly linked to the glass dissolution rate. In addition, the IDF PA model accounts for the alkali-ion exchange process as sodium is leached from the glass and into solution. The effect of temperature, pH, H4SiO4 activity, and the rate of ion-exchange can be parameterized and implemented directly into the PA rate law model. Themore » rate law parameters are derived from laboratory tests with the single-pass flow-through (SPFT) method. To date, rate law parameters have been determined for seven ILAW glass compositions, thus additional rate law parameters on a wider range of compositions will supplement the existing body of data for PA maintenance activities. The data provided in this report can be used by ILAW glass scientists to further the understanding of ILAW glass behavior, by IDF PA modelers to use the rate law parameters in PA modeling efforts, and by Department of Energy (DOE) contractors and decision makers as they assess the IDF PA program.« less

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1]
  1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1365447
Report Number(s):
PNNL-26169; RPT-IGTP-013 Rev. 0.0
830403000
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES

Citation Formats

Neeway, James J., Asmussen, Robert M., Parruzot, Benjamin PG, Cordova, Elsa, Williams, Benjamin D., Leavy, Ian I., Stephenson, John R., and McElroy, Erin M.. FY2016 ILAW Glass Corrosion Testing with the Single-Pass Flow-Through Method. United States: N. p., 2017. Web. doi:10.2172/1365447.
Neeway, James J., Asmussen, Robert M., Parruzot, Benjamin PG, Cordova, Elsa, Williams, Benjamin D., Leavy, Ian I., Stephenson, John R., & McElroy, Erin M.. FY2016 ILAW Glass Corrosion Testing with the Single-Pass Flow-Through Method. United States. doi:10.2172/1365447.
Neeway, James J., Asmussen, Robert M., Parruzot, Benjamin PG, Cordova, Elsa, Williams, Benjamin D., Leavy, Ian I., Stephenson, John R., and McElroy, Erin M.. Fri . "FY2016 ILAW Glass Corrosion Testing with the Single-Pass Flow-Through Method". United States. doi:10.2172/1365447. https://www.osti.gov/servlets/purl/1365447.
@article{osti_1365447,
title = {FY2016 ILAW Glass Corrosion Testing with the Single-Pass Flow-Through Method},
author = {Neeway, James J. and Asmussen, Robert M. and Parruzot, Benjamin PG and Cordova, Elsa and Williams, Benjamin D. and Leavy, Ian I. and Stephenson, John R. and McElroy, Erin M.},
abstractNote = {The inventory of immobilized low-activity waste (ILAW) produced at the Hanford Tank Waste Treatment and Immobilization Plant (WTP) will be disposed of at the near-surface, on-site Integrated Disposal Facility (IDF). When groundwater comes into contact with the waste form, the glass will corrode and radionuclides will be released into the near-field environment. Because the release of the radionuclides is dependent on the dissolution rate of the glass, it is important that the performance assessment (PA) model accounts for the dissolution rate of the glass as a function of various chemical conditions. To accomplish this, an IDF PA model based on Transition State Theory (TST) can be employed. The model is able to account for changes in temperature, exposed surface area, and pH of the contacting solution as well as the effect of silicon concentrations in solution, specifically the activity of orthosilicic acid (H4SiO4), whose concentration is directly linked to the glass dissolution rate. In addition, the IDF PA model accounts for the alkali-ion exchange process as sodium is leached from the glass and into solution. The effect of temperature, pH, H4SiO4 activity, and the rate of ion-exchange can be parameterized and implemented directly into the PA rate law model. The rate law parameters are derived from laboratory tests with the single-pass flow-through (SPFT) method. To date, rate law parameters have been determined for seven ILAW glass compositions, thus additional rate law parameters on a wider range of compositions will supplement the existing body of data for PA maintenance activities. The data provided in this report can be used by ILAW glass scientists to further the understanding of ILAW glass behavior, by IDF PA modelers to use the rate law parameters in PA modeling efforts, and by Department of Energy (DOE) contractors and decision makers as they assess the IDF PA program.},
doi = {10.2172/1365447},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Apr 21 00:00:00 EDT 2017},
month = {Fri Apr 21 00:00:00 EDT 2017}
}

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