Rheological Studies on Pretreated Feed and Melter Feed from C-104 and AZ-102

Bredt, Paul R ; Jagoda, Lynette K ; Rinehart, Donald E

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  :  10.2172/786778
RP-ID  :  PNNL-13359
RP-ID  :  AC06-76RLO1830
RP-ID  :  786778

美国|英语

来源: UNT Digital Library

【 摘 要 】

Rheological and physical properties testing was conducted on actual AZ-102 and C-104 melter feed samples prior to the addition of glass formers and secondary waste products. Analyses were repeated on the C-104 samples following the addition of simulated Sr/TRU secondary waste. Analyses were repeated again following addition of glass formers to both AZ-102 and C-104 samples. Samples from both feeds were tested at the target solids concentrations of 5, 15, and 25 wt%. This data on actual waste is required to validate and qualify results obtained with simulants.