Rheological Studies on Pretreated Feed and Melter Feed from AW-101 and AN-107

Technical Report · Tue Feb 06 00:00:00 EST 2001

DOI:https://doi.org/10.2172/786777· OSTI ID:786777

Bredt, Paul R; Swoboda, Robert G

Rheological and physical properties testing were conducted on actual AN-107 and AW-101 pretreated feed samples prior to the addition of glass formers. Analyses were repeated following the addition of glass formers. The AN-107 and AW-101 pretreated feeds were tested at the target sodium values of nominally 6, 8, and 10 M. The AW-101 melter feeds were tested at these same concentrations, while the AN-107 melter feeds were tested at 5, 6, and 8 M with respect to sodium. These data on actual waste are required to validate and qualify results obtained with simulants.

• Research Organization: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 786777
• Report Number(s): PNNL-13353; 820201000; 820201000; TRN: US0109154
• Resource Relation: Other Information: PBD: 6 Feb 2001
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
RHEOLOGY
PHYSICAL PROPERTIES
MATERIALS TESTING
LIQUID WASTES
RADIOACTIVE WASTE PROCESSING
WASTE FORMS
GLASS
ADDITIVES
CERAMIC MELTERS
SODIUM