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Title: M-Area Mixed Waste Glasses: II: Durability and Viscosity Testing of High Aluminum and Uranium Containing Borosilicate Waste Glasses

Abstract

Radioactive waste sludges that were high in A l2O 3 (14.17 to 29.02 wt%) and U 3O 8 (2.93 to 5.66 wt%) while being simultaneously low in Fe 2O 3 (1.26 to 2.01 wt%) were vitrified into borosilicate glass in the Savannah River Site’s (SRS) M-Area. The overall Na 2O concentrations of borosilicate and soda-lime-silica (SLS) glasses studied at the Savannah River National Laboratory (then the Savannah River Technology Center) prior to startup of the M-Area melter ranged from 6.80 to 27.09 wt%, while the B 2O 3 concentrations ranged from 0.04 to 32.62 wt%.

Authors:
 [1]
  1. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
Publication Date:
Research Org.:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1485264
Report Number(s):
SRNL-STI-2011-00702
DOE Contract Number:  
AC09-08SR22470
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
mixed waste; high alumina waste; high uranium wastes; treatability study; durability testing; TCLP; durability modeling

Citation Formats

Jantzen, C. M. M-Area Mixed Waste Glasses: II: Durability and Viscosity Testing of High Aluminum and Uranium Containing Borosilicate Waste Glasses. United States: N. p., 2018. Web. doi:10.2172/1485264.
Jantzen, C. M. M-Area Mixed Waste Glasses: II: Durability and Viscosity Testing of High Aluminum and Uranium Containing Borosilicate Waste Glasses. United States. doi:10.2172/1485264.
Jantzen, C. M. Tue . "M-Area Mixed Waste Glasses: II: Durability and Viscosity Testing of High Aluminum and Uranium Containing Borosilicate Waste Glasses". United States. doi:10.2172/1485264. https://www.osti.gov/servlets/purl/1485264.
@article{osti_1485264,
title = {M-Area Mixed Waste Glasses: II: Durability and Viscosity Testing of High Aluminum and Uranium Containing Borosilicate Waste Glasses},
author = {Jantzen, C. M.},
abstractNote = {Radioactive waste sludges that were high in Al2O3 (14.17 to 29.02 wt%) and U3O8 (2.93 to 5.66 wt%) while being simultaneously low in Fe2O3 (1.26 to 2.01 wt%) were vitrified into borosilicate glass in the Savannah River Site’s (SRS) M-Area. The overall Na2O concentrations of borosilicate and soda-lime-silica (SLS) glasses studied at the Savannah River National Laboratory (then the Savannah River Technology Center) prior to startup of the M-Area melter ranged from 6.80 to 27.09 wt%, while the B2O3 concentrations ranged from 0.04 to 32.62 wt%.},
doi = {10.2172/1485264},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {11}
}

Technical Report:

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