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

Bredt, Paul R ; Swoboda, Robert G

Pacific Northwest National Laboratory (U.S.)

关键词: 12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities;    Sodium;    Liquid Wastes;    36 Materials Science;    Radioactive Waste Processing;   

DOI  :  10.2172/786777
RP-ID  :  PNNL-13353
RP-ID  :  AC06-76RLO1830
RP-ID  :  786777

美国|英语

来源: UNT Digital Library

【 摘 要 】

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.