Masters Theses

Abstract

"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.

Advisor(s)

Day, D. E.

Department(s)

Materials Science and Engineering

Degree Name

M.S. in Ceramic Engineering

Sponsor(s)

United States. Department of Energy

Publisher

University of Missouri--Rolla

Publication Date

Fall 2002

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

Pagination

xiv, 115 pages

Rights

© 2002 Robert Douglas Leerssen, All rights reserved.

Document Type

Thesis - Open Access

File Type

text

Language

English

Library of Congress Subject Headings

Glass
Radioactive wastes -- Vitrification
Ceramic materials -- Environmental aspects

Thesis Number

T 8128

Print OCLC #

53103065

Electronic OCLC #

244393863

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