"The current study investigates the feasibility of using iron phosphate glass for the immobilization of nuclear wastes that have limited solubility in the current borosilicate glass used for vitrification. These wastes contain elements such as sulfur and phosphorus, which have proven problematic (causing phase separation at >1 wt%) for vitrification in borosilicate glasses, as well as having a high soda content (50-75 wt%) which also limits wasteloading"--Abstract, page iv.
Day, D. E.
Materials Science and Engineering
M.S. in Ceramic Engineering
United States. Department of Energy
University of Missouri--Rolla
Journal article titles appearing in thesis/dissertation
- Iron phosphate glass for the vitrification of INEEL sodium bearing waste
- Iron phosphate glass for the vitrification of Hanford low activity waste with high sulfur content
xiv, 115 pages
© 2002 Robert Douglas Leerssen, All rights reserved.
Thesis - Open Access
Library of Congress Subject Headings
Radioactive wastes -- Vitrification
Ceramic materials -- Environmental aspects
Print OCLC #
Electronic OCLC #
Link to Catalog Recordhttp://laurel.lso.missouri.edu/record=b4996693~S5
Leerssen, Robert Douglas, "Iron phosphate glass for the vitrification of INEEL sodium bearing waste and Hanford low activity waste" (2002). Masters Theses. 4621.