Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing
Journal Article
·
· Journal of Nuclear Materials
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Energy Northwest, Richland, WA (United States)
- Argonne National Lab. (ANL), Lemont, IL (United States)
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
Here, this paper provides an overview of research evaluating the use of lead tellurite glass as a waste form for salt wastes from electrochemical reprocessing of used nuclear fuel. The efficacy of using lead tellurite glass to immobilize three different salt compositions was evaluated: a LiCl-Li2O oxide reduction salt containing fission products from oxide fuel, a LiCl-KCl eutectic salt containing fission products from metallic fuel, and SrCl2. Physical and chemical properties of glasses made with these salts were characterized with X-ray diffraction, bulk density measurements, differential thermal analysis, chemical durability tests, scanning and transmission electron microscopies, and energy-dispersive X-ray spectroscopy. These glasses were found to accommodate high salt concentrations and have high densities, but further development is needed to improve chemical durability.
- Research Organization:
- Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- Grant/Contract Number:
- AC05-76RL01830
- OSTI ID:
- 1379949
- Alternate ID(s):
- OSTI ID: 1411170
OSTI ID: 1549773
OSTI ID: 1395275
OSTI ID: 1398210
- Report Number(s):
- PNNL-SA--125402; PII: S0022311517305561
- Journal Information:
- Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 495; ISSN 0022-3115
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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