@article{c00d6c236d37429894f8eae836d21391,
title = "Compositional dependence of crystallization and chemical durability in alkali aluminoborosilicate glasses",
abstract = "This study aims to understand the impact of composition on crystallization and chemical durability in alkali aluminoborosilicate based model nuclear waste glasses designed in the peralkaline, metaluminous and peraluminous regimes. The glasses have been thermally treated using the canister centerline cooling (CCC) schedule. The chemical durability of both parent and CCC-treated glasses has been assessed by product consistency test (PCT-B) for 120 days. The peraluminous glasses exhibit the highest dissolution rates, followed by peralkaline and metaluminous glasses. In general, increasing B2O3 content in glasses tends to suppress nepheline formation, thus, decreasing the negative impact of nepheline on durability of the final waste form. However, higher B2O3 content itself may result in detrimental impact on the durability of the final waste form. The thermal history has been shown to have a significant impact on the durability of the glasses.",
keywords = "Chemical durability, Crystallization, Glass, Nuclear waste",
author = "Ambar Deshkar and Benjamin Parruzot and Youngman, {Randall E.} and Ozgur Gulbiten and Vienna, {John D.} and Ashutosh Goel",
note = "Funding Information: Nearly five decades of plutonium production in the support of U.S. defense programs has generated ∼56 million gallons of radioactive and chemical wastes at the U.S. Department of Energy's (DOE) Hanford Site in Washington state [1] . The waste is currently stored inside 177 underground tanks, wherein the contents of these tanks include a complex sludge, salt cake, and supernate mixed radioactive waste [1] . Bechtel National Inc. is constructing the Hanford Tank Waste Treatment and Immobilization Plant to vitrify the high-level waste (HLW) and low-activity waste (LAW) fractions into alkali-aluminoborosilicate-based glassy waste forms [2–4] . The waste-to-glass conversion will be achieved by mixing glass-forming precursors like SiO 2 and H 3 BO 3 (as a source of B 2 O 3 ) in the waste feed followed by melting the mixture in Joule heated ceramic melters (JHCM), and subsequently pouring the melt into stainless steel canisters to cool and solidify [5–7] . While SiO 2 has been chosen as the primary glass network former, B 2 O 3 has been chosen as a flux to lower the melting temperature of the batch (waste feed + glass-forming oxides), to enable the vitrification of waste at ∼1150 °C. As per the current strategy for nuclear waste disposal, the steel canisters containing the vitrified HLW glasses will be transported to a geological repository, while the LAW steel containers will be managed at an on-site integrated disposal facility (IDF). Funding Information: This material is based upon work supported by the US Department of Energy (DOE), Office of River Protection, Waste Treatment & Immobilization Plant (WTP), through contract number 89304018CEM000006, and National Science Foundation under Grant No. 2034871 . The authors are thankful to Dr. Nicholas Stone-Weiss (Corning Incorporated) and Dr. Jim Neeway (PNNL) for their suggestions/discussion. The authors would like to thank Dr. Albert Kruger (US Department of Energy) for the technical oversight of the work. Publisher Copyright: {\textcopyright} 2022",
year = "2022",
month = aug,
day = "15",
doi = "https://doi.org/10.1016/j.jnoncrysol.2022.121694",
language = "American English",
volume = "590",
journal = "Journal of Non-Crystalline Solids",
issn = "0022-3093",
publisher = "Elsevier",
}