LIQUIDUS TEMPERATURE STUDIES IN SUPPORT OF THE INCORPORATION OF SMALL COLUMN ION EXCHANGE STREAMS IN DEFENSE WASTE PROCESSING FACILITY HIGH LEVEL WASTE GLASS

2011 ◽  
Author(s):  
K. Fox ◽  
F. Johnson ◽  
T. Edwards
Keyword(s):  
Ion Exchange ◽  
Liquidus Temperature ◽  
Waste Glass ◽  
High Level Waste ◽  
Waste Processing ◽  
Small Column ◽  
Processing Facility ◽  
High Level

scholarly journals Status of the Development of In-Tank/At-Tank Separations Technologies for High-Level Waste Processing for the U.S. Department of Energy

2011 ◽  
Author(s):  
William R. Wilmarth ◽  
Nicholas P. Machara ◽  
Reid A. Peterson ◽  
Sheryl R. Bush
Keyword(s):  
South Carolina ◽  
Ion Exchange ◽  
Development Program ◽  
High Level Waste ◽  
Waste Processing ◽  
Savannah River ◽  
Separation Processes ◽  
Processing Facility ◽  
High Level ◽  
The U.S

Within the U.S. Department of Energy’s (DOE) Office of Technology Innovation and Development, the Office of Waste Processing manages a research and development program related to the treatment and disposition of radioactive waste. At the Savannah River (South Carolina) and Hanford (Washington) Sites, approximately 90 million gallons of waste are distributed among 226 storage tanks (grouped or collocated in “tank farms”). This waste may be considered to contain mixed and stratified high activity and low activity constituent waste liquids, salts and sludges that are collectively managed as high level waste (HLW). A large majority of these wastes and associated facilities are unique to the DOE, meaning many of the programs to treat these materials are “first-of-a-kind” and unprecedented in scope and complexity. As a result, the technologies required to disposition these wastes must be developed from basic principles, or require significant reengineering to adapt to DOE’s specific applications. Of particular interest recently, the development of In-tank or At-Tank separation processes have the potential to treat waste with high returns on financial investment. The primary objective associated with In-Tank or At-Tank separation processes is to accelerate waste processing. Insertion of the technologies will (1) maximize available tank space to efficiently support permanent waste disposition including vitrification; (2) treat problematic waste prior to transfer to the primary processing facilities at either site (i.e., Hanford’s Waste Treatment and Immobilization Plant (WTP) or Savannah River’s Salt Waste Processing Facility (SWPF)); and (3) create a parallel treatment process to shorten the overall treatment duration. This paper will review the status of several of the R&D projects being developed by the U.S. DOE including insertion of the ion exchange (IX) technologies, such as Small Column Ion Exchange (SCIX) at Savannah River. This has the potential to align the salt and sludge processing life cycle, thereby reducing the Defense Waste Processing Facility (DWPF) mission by 7 years. Additionally at the Hanford site, problematic waste streams, such as high boehmite and phosphate wastes, could be treated prior to receipt by WTP and thus dramatically improve the capacity of the facility to process HLW. Treatment of boehmite by continuous sludge leaching (CSL) before receipt by WTP will dramatically reduce the process cycle time for the WTP pretreatment facility, wile treatment of posphate will significantly reduce the number of HLW borosilicate glass canisters produced at the WTP. These and other promising technologies will be discussed.

scholarly journals The effect of high-level waste glass composition on spinel liquidus temperature

2014 ◽  
Vol 384 ◽  
pp. 32-40 ◽  
Author(s):  
Pavel Hrma ◽  
Brian J. Riley ◽  
Jarrod V. Crum ◽  
Josef Matyas
Keyword(s):  
Liquidus Temperature ◽  
Glass Composition ◽  
Waste Glass ◽  
High Level Waste ◽  
High Level

scholarly journals Implementation of flowsheet change to minimize hydrogen and ammonia generation during chemical processing of high level waste in the Defense Waste Processing Facility

2016 ◽  
Author(s):  
Dan P. Lambert ◽  
Wesley H. Woodham ◽  
Matthew S. Williams ◽  
J. David Newell ◽  
Michelle C. Luther ◽  
...  
Keyword(s):  
High Level Waste ◽  
Chemical Processing ◽  
Waste Processing ◽  
Processing Facility ◽  
High Level

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.

scholarly journals High Level Waste System Impacts from Small Column Ion Exchange Implementation

2005 ◽  
Author(s):  
D. J. McCabe ◽  
L. L. Hamm ◽  
S. E. Aleman ◽  
D. K. Peeler ◽  
C. C. Herman ◽  
...  
Keyword(s):  
Ion Exchange ◽  
High Level Waste ◽  
Small Column ◽  
High Level

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.

Liquidus Temperature of Spinel Precipitating High-Level Waste Glasses

1996 ◽  
Vol 465 ◽  
Author(s):  
M. Mika ◽  
M. J. Schweiger ◽  
J. D. Vienna ◽  
P. Hrma
Keyword(s):  
Mixture Models ◽  
Crystalline Phase ◽  
Liquidus Temperature ◽  
Glass Composition ◽  
High Level Waste ◽  
Hanford Site ◽  
High Iron ◽  
Negative Effect ◽  
High Level ◽  
Glass Viscosity

ABSTRACTThe liquidus temperature (TL) often limits the loading of high-level waste in glass through the constraint that TL must be at least 100°C below the temperature at which the glass viscosity is 5 Pa-s. In this study, values of TL for spinel primary crystalline phase were measured as a function of glass composition. The test glasses were based on high-iron Hanford Site tank wastes. All studied glasses precipitated spinel (Ni,Fe,Mn)(Cr,Fe)2O4 as the primary crystalline phase. TL was increased by additions of Cr2O3, NiO, Al2O3, Fe2O3, MgO, and MnO; while Li2O, Na2O, B2O3, and SiO2 had a negative effect. Empirical mixture models were fitted to data.

Neptunium Speciation in Humic Acid-rich Clay Water upon Interaction With Radioactive Waste Glass Samples

2002 ◽  
Vol 757 ◽  
Author(s):  
V. Pirlet ◽  
P. Van Iseghem
Keyword(s):  
Humic Substances ◽  
Humic Acids ◽  
Specific Interaction ◽  
Waste Glass ◽  
High Level Waste ◽  
Boom Clay ◽  
Dissolution Tests ◽  
Vis Spectroscopy ◽  
Doped Glasses ◽  
High Level

ABSTRACTOrganic complexes of actinides are known to occur upon interaction of high level waste glass and Boom Clay which is a potential host rock formation for disposal of high level waste in Belgium. The solubility and mobility of 237Np, one of the most critical radionuclides, can be affected by the high dissolved organic carbon content of the Boom Clay porewater through complexation with the humic substances. The influence of humic substances on the Np behaviour is considered through dissolution tests of Np-doped glasses in Boom Clay water and through fundamental study of the specific interaction between Np(IV) and the humic acids using spectroscopic techniques. High Np(IV) concentrations are found in the glass dissolution tests. These concentrations are higher than what we should expect from the solubility of Np(OH)4, the solubility limiting solid phase predicted under the reducing conditions and pH prevailing in Boom Clay. Studying the specific interaction of Np(IV) with humic acids in Boom Clay porewater, high soluble Np concentrations are also measured and two main tetravalent Np-humate species are observed by UV-Vis spectroscopy. The two species are interpreted in terms of mixed hydroxo-humate complexes, Np(OH)xHA with x = 3 or 4. These species are the most likely species that can form according to the pH working conditions. Using thermodynamic simplified approaches, high complexation constants, i.e. log β131 and log β141 respectively equal to 46 and 51.6, are calculated for these species under the Boom Clay conditions.Comparing the spectroscopic results of the dissolution tests with the study of the interaction of Np(IV) with humic substances, we can conclude that the complexation of Np(IV) with the humic acids may occur and increases the solubility of Np(OH)4 upon interaction of a Np-doped glass and the Boom Clay porewater.

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