scholarly journals Formulation of SYNROC-D additives for Savannah River Plant high-level radioactive waste. [ADSYN code]

1981 ◽  
Author(s):  
F.J. Ryerson ◽  
K. Burr ◽  
R. Rozsa
Keyword(s):  
Radioactive Waste ◽  
Savannah River ◽  
High Level Radioactive Waste ◽  
Savannah River Plant ◽  
High Level

scholarly journals High-Level Radioactive Insoluble Waste Preparation for Vitrification

1984 ◽  
Vol 44 ◽  
Author(s):  
B. A. Hamm ◽  
R. E. Eibling ◽  
M. A. Ebra ◽  
T. Motyka ◽  
H. D. Martin
Keyword(s):  
Radioactive Waste ◽  
Borosilicate Glass ◽  
Savannah River ◽  
Soluble Salts ◽  
High Level Radioactive Waste ◽  
Savannah River Plant ◽  
High Level

AbstractAt the Savannah River Plant (SRP), a process has been developed for immobilizing high-level radioactive waste in a borosilicate glass. The waste is currently stored as soluble salts and insoluble solids. Insoluble waste as stored requires further processing before vitrification is possible. The processes required have been developed and demonstrated with actual waste. They include removal of aluminum in some waste, washing soluble salts out of the insoluble waste, and mercury stripping. Each of the processes and the results with actual SRP waste will be discussed. The benefits of each step will also be included.

Mercury Reduction and Removal During High-Level Radioactive Waste Processing and Vitrification

1981 ◽  
Vol 6 ◽  
Author(s):  
Russell E. Eibling ◽  
John R. fowler
Keyword(s):  
Radioactive Waste ◽  
Formic Acid ◽  
Borosilicate Glass ◽  
Processing Temperature ◽  
Savannah River ◽  
High Level Radioactive Waste ◽  
Savannah River Plant ◽  
Reference Process ◽  
Glass Melter ◽  
High Level

ABSTRACTA reference process for immobilizing the high-level radioactive waste in borosilicate glass has been developed at the Savannah River Plant. This waste contains a substantial amount of mercury from separations processing. Because mercury will not remain in borosilicate glass at the processing temperature, mercury must be removed before vitrification or must be handled in the off-gas system. A process has been developed to remove mercury by reduction with formic acid prior to vitrification. Additional benefits of formic acid treatment include improved sludge handling and glass melter redox control.

scholarly journals Vitrification of High-Level Radioactive Waste in a Small-Scale Joule-Heated Ceramic Melter

1981 ◽  
Vol 6 ◽  
Author(s):  
Gerald B. Woolsey ◽  
M. John Plodinec
Keyword(s):  
Radioactive Waste ◽  
Large Scale ◽  
Liquid Waste ◽  
Glass Frit ◽  
Small Scale ◽  
Savannah River ◽  
Savannah River Plant ◽  
Reference Process ◽  
High Level ◽  
Large Scale Tests

ABSTRACTVitrification is the reference process for the immobilization of radioactive waste from the production of defense materials at the Savannah River Plant (SRP). Since 1979, a small vitrification facility (1 Ib/hr) has been operated at the Savannah River Laboratory using actual SRP waste. In previous studies. dried waste was fed to this smaller melter. This report discusses direct feeding of actual liquid-waste slurries to the small melter. These liquidfeeding tests demonstrated that addition of premelted glass frit to the waste slurry reduces the amount of material volatilized. Results of these tests are in accord with results of large-scale tests with actual waste.

scholarly journals Remote Inspection of a High Level Radioactive Waste Storage Tank for Cracking, Thinning, and Pitting

2003 ◽  
Author(s):  
J. B. Elder ◽  
B. J. Wiersma ◽  
R. L. Sindelar
Keyword(s):  
Radioactive Waste ◽  
Crack Detection ◽  
Savannah River ◽  
High Level Radioactive Waste ◽  
Waste Storage ◽  
Wall Loss ◽  
High Level ◽  
Remote Inspection ◽  
Radioactive Waste Storage

Several of the high level radioactive waste storage tanks at the Savannah River Site (SRS) have been in service nearly 50 years. Periodic visual and ultrasonic (UT) nondestructive examinations (NDE) have been performed on the tanks to monitor the effects of service. These inspections revealed that several of the older tanks had suffered cracking as detected by through-wall visual indications. A new UT in-service inspection program has been recently established to provide for detection and characterization of cracking, thinning, or pitting of the sidewalls of the waste tanks. The program specifies examination of regions of the tank that would be most susceptible to corrosion attack, and to characterize the flaws and demonstrate acceptance to protect against potential leakage and instability. This paper summarizes the implementation of the program and inspection results for a tank that has been in service for over 40 years. No indications of reportable wall loss or pitting were detected. All thickness readings were above minimum design thickness. Several small indications of thinning were detected. The crack detection and sizing examinations detected five previously undetected indications, four of which were only partially through wall. The lengths of cracks that were examined are slightly longer than expected, but well below instability lengths.

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