Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing

Journal Article · Wed Aug 30 00:00:00 EDT 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/J.JNUCMAT.2017.08.037· OSTI ID:1379949

Riley, Brian J. ^[1]; Kroll, Jared O. ^[1]; Peterson, Jacob A. ^[1]; Pierce, David A. ^[2]; Ebert, William L. ^[3]; Williams, Benjamin D. ^[1]; Snyder, Michelle M. V. ^[1]; Frank, Steven M.  ^[4]; George, Jaime L.  ^[1]; Kruska, Karen ^[1]

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1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
2. Energy Northwest, Richland, WA (United States)
3. Argonne National Lab. (ANL), Lemont, IL (United States)
4. Idaho National Lab. (INL), Idaho Falls, ID (United States)

• Research Organization: Pacific Northwest National Lab. (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: 1395275; OSTI ID: 1549773
• Report Number(s): PNNL-SA-125402; PII: S0022311517305561
• Journal Information: Journal of Nuclear Materials, Vol. 495; ISSN 0022-3115
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
Tellurite glass
Strontium chloride
Pyroprocessing
Oxide reduction