Immobilization of Spent Nuclear Fuel in Iron Phosphate Glass
Abstract
Twenty-four iron phosphate compositions (15 wt% wasteloading) were evaluated to determine their suitability for vitrifying Al-clad, highly enriched uranium, spent nuclear fuel (SNF). In half the compositions melted, 80 wt% of the Al2O3 in the simulated SNF was removed prior to vitrification. All twenty-four compositions formed homogeneous glasses, many at temperatures as low as 1150°C. As little as 2.5 wt% Na2O decreased melt viscosity and increased alumina solubility in those glasses of higher alumina contents (7.2 wt% Al2O3). None of the glasses contained undissolved uranium compounds as has been found in borosilicate glasses containing as little 4.4 wt% UO2. The chemical durability (measured by the product consistency test (PCT)) of the iron phosphate wasteforms is as good as, and in many cases up to 15 times better than the approved reference material (ARM-1) borosilicate glass.
Recommended Citation
M. G. Mesko and D. E. Day, "Immobilization of Spent Nuclear Fuel in Iron Phosphate Glass," Journal of Nuclear Materials, Elsevier, Jun 1999.
The definitive version is available at https://doi.org/10.1016/S0022-3115(99)00020-3
Department(s)
Materials Science and Engineering
Sponsor(s)
Savannah River Technology Center (U.S.)
International Standard Serial Number (ISSN)
0022-3115
Document Type
Article - Journal
Document Version
Citation
File Type
text
Language(s)
English
Rights
© 1999 Elsevier, All rights reserved.
Publication Date
01 Jun 1999
