Viscosity of glass‐forming melt at the bottom of high‐level waste melter‐feed cold caps: Effects of temperature and incorporation of solid components

2019 ◽  
Vol 103 (3) ◽  
pp. 1615-1630
Author(s):  
Seung Min Lee ◽  
Benjamin P. McCarthy ◽  
Pavel Hrma ◽  
Jaehun Chun ◽  
Richard Pokorny ◽  
...  
Keyword(s):  
High Level Waste ◽  
Glass Forming ◽  
Effects Of Temperature ◽  
High Level

Thermodynamic model for the solubility of thorium dioxide in the Na+-Cl--OH--H2O system at 23°C and 90°C

2000 ◽  
Vol 88 (5) ◽  
Author(s):  
Dhanpat Rai ◽  
Dean A. Moore ◽  
C.S. Oakes ◽  
Mikazu Yui
Keyword(s):  
Thermodynamic Model ◽  
High Level Waste ◽  
Thorium Dioxide ◽  
Ambient Temperatures ◽  
Oxide Phases ◽  
Solubility Studies ◽  
Effects Of Temperature ◽  
Solubility Products ◽  
High Level ◽  
Waste Repositories

Data are extremely limited on the effects of temperature on crystallinity and the resulting changes in solubility products of thermally transformed thorium oxide phases. Such data are required to reliably predict thorium behavior in high-level waste repositories where higher than ambient temperatures are expected. Solubility studies were conducted as a function of pH and time and at 0.1 M NaCl for 1) ThO

Demonstration of the defense waste processing facility vitrification process for tank 42 radioactive sludge – melter feed preparation

1999 ◽  
Vol 556 ◽  
Author(s):  
T. L. Fellinger ◽  
N. E. Bibler ◽  
K. M. Marshall ◽  
C. L. Crawford ◽  
M. S. Hay
Keyword(s):  
Formic Acid ◽  
Weight Percent ◽  
High Level Waste ◽  
Waste Processing ◽  
Savannah River ◽  
Glass Forming ◽  
Process Flowsheet ◽  
Processing Facility ◽  
High Level ◽  
River Site

AbstractThe Defense Waste Processing Facility (DWPF), at the Savannah River Site (SRS), is processing and immobilizing the radioactive high level waste sludge at SRS into a durable borosilicate glass for final geological disposal. The DWPF is currently processing the second, million gallon batch of radioactive sludge. This second batch is primarily from Tank 42. Each time a new batch of radioactive sludge is to be processed by the DWPF, the process flowsheet is to be tested and demonstrated to ensure an acceptable melter feed and glass can be made. This demonstration was completed in the Shielded Cells Facility in the Savannah River Technology Center at SRS.This paper presents the processing and offgas data, and compositional analyses obtained during the preparation of a melter feed for this demonstration. A second paper in this conference describes the properties of the glass produced from this feed. The demonstration used Tank 42 sludge slurry and the DWPF process control strategy for blending the sludge slurry with Frit 200 to make an acceptable melter feed. To prepare feed for the melter, the flowsheet requires that the radioactive sludge slurry be treated with nitric and formic acid to adjust rheology and remove mercury. During this step, hydrogen is formed from the decomposition of the formic acid. The acidified sludge slurry is then mixed with the prescribed amount of glass forming frit and evaporated to the proper weight percent solids to prepare feed to the melter. During this step hydrogen is also formed. Results indicate that the H2 generation rate is below the DWPF safety limits and an acceptable melter feed was produced.

Demonstration of the defense waste processing facility vitrification process for tank 42 radioactive sludge – glass preparation and characterization

1999 ◽  
Vol 556 ◽  
Author(s):  
Ned E. Bibler ◽  
Terri L. Fellinger ◽  
Kathryn M. Marshall ◽  
Charles L. Crawford ◽  
A. D. Cozzi ◽  
...  
Keyword(s):  
High Level Waste ◽  
Waste Processing ◽  
Savannah River ◽  
Glass Forming ◽  
Waste Sludge ◽  
Process Flowsheet ◽  
Processing Facility ◽  
High Level ◽  
River Site

AbstractThe Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) is currently processing and immobilizing the radioactive high level waste sludge at SRS into a durable borosilicate glass for final geological disposal. The DWPF has recently finished processing the first radioactive sludge batch, and is ready for the second batch ofradioactive sludge. The second batch is primarily sludge from Tank 42. Before processing this batch in the DWPF, the DWPF process flowsheet has to be demonstrated with a sample of Tank 42 sludge to ensure that an acceptable melter feed and glass can be made. This demonstration was recently completed in the Shielded Cells Facility at SRS. An earlier paper in these proceedings described the sludge composition and processes necessary for producing an acceptable melter feed [1]. This paper describes the preparation and characterization of the glass from that demonstration. Results substantiate that Tank 42 sludge after mixing with the proper amount of glass forming frit (Frit 200) can be processed to make an acceptable glass.

Effects of Aging on the Solubility of Palladium

1995 ◽  
Vol 412 ◽  
Author(s):  
C. Oda ◽  
H. Yoshikawa ◽  
M. Yui
Keyword(s):  
Aqueous Solution ◽  
Aging Time ◽  
Room Temperature ◽  
High Level Waste ◽  
Anaerobic Conditions ◽  
Dilute Aqueous Solution ◽  
Waste Repository ◽  
Ph Range ◽  
Effects Of Aging ◽  
High Level

AbstractPalladium solubility was measured in a dilute aqueous solution at room temperature in the pH range from 3 to 13 under anaerobic conditions. Crystalline Pd metal was clearly visible and the concentration of palladium in solution decreased gradually with aging time. The palladium concentrations in solution were less than 9.4×10-10M in the pH range from 4 to 10 and increased to 10-7M in the pH range greater than 10. This study suggests that palladium concentrations in certain high-level waste repository environments may be limited by Pd metal and may be less than 10-9M.

Performance assessment of the disposal of vitrified high-level waste in a clay layer

2001 ◽  
Vol 298 (1-2) ◽  
pp. 125-135 ◽  
Author(s):  
Dirk Mallants ◽  
Jan Marivoet ◽  
Xavier Sillen
Keyword(s):  
Performance Assessment ◽  
High Level Waste ◽  
Clay Layer ◽  
High Level
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