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Initial demonstration of DWPF process and product control strategy using actual radioactive waste

Description: The Defense Waste Processing Facility at the Savannah River Site (SRS) will vitrify high-level nuclear waste into borosilicate glass. The waste will be mixed with properly formulated glass-making frit and fed to a melter at 1150{degrees}C. Process control and product quality are ensured by proper control of the melter feed composition. Algorithms have been developed to predict the processability of the melt and the durability of the final glass based on this feed composition. To test these algo… more
Date: January 1, 1991
Creator: Andrews, M. K.; Bibler, N. E.; Jantzen, Carol M. & Beam, D. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Durability of simulated DWPF annealed glasses

Description: Simulated high-level waste glass samples of the DWPF projected compositions were annealed at various times and temperatures in order to develop time-temperature-transformation diagrams. These heat treated glasses were subjected to the Product Consistency Test (PCT) to evaluate glass durability. The B, Li, and Na concentrations in the leachate (the PCT results) were compared to the PCT results of the Environmental Assessment benchmark glass. Durability as a function of glass composition and crys… more
Date: March 1, 1993
Creator: Andrews, M. K.; Cicero, C. A.; Marra, S. L. & Beam, D. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Durability of glasses vitrified from high copper feed in the 774 Research Melter

Description: Small scale crucible studies were performed by Schumacher to examine the effects of formate and nitrate on glass redox at high copper levels. The results of the crucible studies were used to determine the regions where copper precipitates in the glass. However, durability tests were not performed on the glass samples. Studies were performed in the 774 Research Melter using a simulated feed from the Purex 4 Campaign in the Integrated DWPF Melter System (IDMS). Three runs were performed with this… more
Date: April 28, 1993
Creator: Andrews, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of TCLP and long-term PCT performance on low-level mixed waste glasses

Description: The Mixed Waste Integrated Program (MWIP) of the US Department of Energy (DOE) is currently investigating technologies for conversion of low-level mixed waste (LLMW) into a form suitable for permanent disposal. Vitrification is one of the preferred technologies since it is capable of consistently producing a durable, leach resistant wasteform, while simultaneously minimizing disposal volumes. Since vitrification of LLMW is a relatively new concept, final wasteform specifications have not been d… more
Date: June 1, 1994
Creator: Cicero, C. A.; Andrews, M. K. & Bickford, D. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Trip report: Marshall Space Center computed tomography

Description: BIR Inc. is a small company out of the Chicago area which sells equipment for producing images by tomography. They have built a relatively large instrument, called ACTIS, for NASA at the Marshall Space Center in Huntsville, Alabama and still gave access to this instrument. BIR has a grant from the Department of Energy (DOE) to determine the utility of computed tomography (CT) for characterization of nuclear and hazardous waste within the DOE complex. As part of this effort, the potential of thi… more
Date: December 31, 1991
Creator: Harbour, J. R. & Andrews, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Vitrification in the presence of salts

Description: Glass is an advantageous material for the immobilization of nuclear wastes because of the simplicity of processing and its unique ability to accept a wide variety of waste elements into its network structure. Unfortunately, some anionic species which are present in the nuclear waste streams have only limited solubility in oxide glasses. This can result in either vitrification concerns or it can affect the integrity, of the final vitrified waste form. The presence of immiscible salts can also co… more
Date: July 1, 1994
Creator: Marra, J. C.; Andrews, M. K. & Schumacher, R. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Radioactive demonstration of DWPF product control strategy

Description: The effectiveness of the product and process control strategies that will be utilized by the Defense Waste Processing Facility (DWPF) was demonstrated during a campaign in the Shielded Cells Facility (SCF) of the Savannah River Technology Center (SRTC). The remotely operated process included the preparation of the melter feed, vitrification in a slurry-fed 1/100th scale melter and analysis of the glass product both for its composition and durability. The campaign processed approximately 10 kg (… more
Date: April 22, 1992
Creator: Andrews, M. K. & Bibler, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Trip report: Marshall Space Center computed tomography

Description: BIR Inc. is a small company out of the Chicago area which sells equipment for producing images by tomography. They have built a relatively large instrument, called ACTIS, for NASA at the Marshall Space Center in Huntsville, Alabama and still gave access to this instrument. BIR has a grant from the Department of Energy (DOE) to determine the utility of computed tomography (CT) for characterization of nuclear and hazardous waste within the DOE complex. As part of this effort, the potential of thi… more
Date: January 1, 1991
Creator: Harbour, J. R. & Andrews, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radioactive demonstration of DWPF product control strategy

Description: The effectiveness of the product and process control strategies that will be utilized by the Defense Waste Processing Facility (DWPF) was demonstrated during a campaign in the Shielded Cells Facility (SCF) of the Savannah River Technology Center (SRTC). The remotely operated process included the preparation of the melter feed, vitrification in a slurry-fed 1/100th scale melter and analysis of the glass product both for its composition and durability. The campaign processed approximately 10 kg (… more
Date: April 22, 1992
Creator: Andrews, M. K. & Bibler, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Initial demonstration of DWPF process and product control strategy using actual radioactive waste

Description: The Defense Waste Processing Facility at the Savannah River Site (SRS) will vitrify high-level nuclear waste into borosilicate glass. The waste will be mixed with properly formulated glass-making frit and fed to a melter at 1150{degrees}C. Process control and product quality are ensured by proper control of the melter feed composition. Algorithms have been developed to predict the processability of the melt and the durability of the final glass based on this feed composition. To test these algo… more
Date: December 31, 1991
Creator: Andrews, M. K.; Bibler, N. E.; Jantzen, Carol M. & Beam, D. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Time- temperature- transformation- diagrams for DWPF projected glass compositions

Description: The Department of Energy`s Waste Acceptance Product Specifications (WAPS) require that time-temperature-transformation diagrams be developed for each of the DWPF high-level waste glass compositions. This information will be useful in understanding the crystallization behavior during melter idling, accident scenarios, and storage. Simulated high level waste glass samples were annealed at temperatures varying from 400-1100{degrees}C for times varying from 45 minutes to 32 days. The glasses were c… more
Date: March 1, 1993
Creator: Marra, S. L.; Andrews, M. K. & Cicero, C. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Phase stability determinations of DWPF waste glasses

Description: The high-level radioactive wastes stored at Savannah River, will be immobilized in borosilicate glass in the Defense Waste Processing Facility (DWPF). Waste Acceptance Preliminary Specifications require that time-temperature-transformation (TTT) curves be provided for expected DWPF compositions, in order to predict the durability of the waste form. In order to derive these TTT curves, samples of simulated glasses are being heat treated and then analyzed. The seven simulated glasses include blen… more
Date: September 1, 1992
Creator: Andrews, M. K.; Cicero, C. A.; Marra, S. L.; Beam, D. C. & Jantzen, Carol M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin

Description: When immobilizing into borosilicate glass the radionuclides in the caustic high-level radioactive wastes stored in the USA, the soluble fission product Cs-137 has to be removed from supernates of the wastes. In the current processes zeolites or an organic precipitant will be used to remove the Cs. These solids are then treated further and mixed with the radioactive sludges and vitrified into a borosilicate glass. This paper describes the vitrification of a mixture resulting from using a new pro… more
Date: January 1, 1991
Creator: Bibler, N. E.; Bibler, J. P.; Andrews, M. K. & Jantzen, Carol M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Research and development task plan: Shielded Cells Batch 1 campaign. Revision 2

Description: The primary objectives of this task are to characterize the sludge, to identify any unexpected processing problems, and to demonstrate the ability to make an acceptable glass product. Another objective is to determine the amount of washing that the sludge from Tank 42 requires. The 500 ml glass Sludge Receipt and Adjustment Tank (SRAT) and the 100 L stainless steel SRAT have already been used in the Shielded Cells to demonstrate the process using samples from other tanks. The melter and off-gas… more
Date: October 8, 1993
Creator: Andrews, M. K.; Bibler, N. E.; Ferrara, D. M.; Ha, B. C. & Hay, M. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analytical study plan: Shielded Cells batch 1 campaign; Revision 1

Description: Radioactive operations in the Defense Waste Processing Facility (DWPF) will require that the Savannah River Technology Center (SRTC) perform analyses and special studies with actual Savannah River Site (SRS) high-level waste sludge. SRS Tank 42 and Tank 51 will comprise the first batch of sludge to be processed in the DWPF. Approximately 25 liters of sludge from each of these tanks will be characterized and processed in the Shielded Cells of SRTC. During the campaign, processes will include slu… more
Date: October 4, 1993
Creator: Bibler, N. E.; Ha, B. C.; Hay, M. S.; Ferrara, D. M. & Andrews, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin

Description: When immobilizing into borosilicate glass the radionuclides in the caustic high-level radioactive wastes stored in the USA, the soluble fission product Cs-137 has to be removed from supernates of the wastes. In the current processes zeolites or an organic precipitant will be used to remove the Cs. These solids are then treated further and mixed with the radioactive sludges and vitrified into a borosilicate glass. This paper describes the vitrification of a mixture resulting from using a new pro… more
Date: December 31, 1991
Creator: Bibler, N. E.; Bibler, J. P.; Andrews, M. K. & Jantzen, Carol M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Phase stability determinations of DWPF waste glasses. [Defense Waste Processing Facility]

Description: The high-level radioactive wastes stored at Savannah River, will be immobilized in borosilicate glass in the Defense Waste Processing Facility (DWPF). Waste Acceptance Preliminary Specifications require that time-temperature-transformation (TTT) curves be provided for expected DWPF compositions, in order to predict the durability of the waste form. In order to derive these TTT curves, samples of simulated glasses are being heat treated and then analyzed. The seven simulated glasses include blen… more
Date: January 1, 1992
Creator: Andrews, M. K.; Cicero, C. A.; Marra, S. L.; Beam, D. C. & Jantzen, Carol M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Glass formulation development and testing for the vitrification of Oak Ridge tank waste

Description: As part of joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC), radioactive waste from four different ORNL tank farms will be immobilized. This work, which is funded by the DOE Office of Science and Technology, is designed to create a direct comparison between grouting and vitrification technologies. SRTC efforts have been focused on developing and testing glass formulations for the vitrification of the tank wastes. The radioactive wast… more
Date: June 17, 1997
Creator: Andrews, M. K. & Workman, P. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Glass Formulation Development for the Vitrification of Oak Ridge Tank Waste

Description: Radioactive waste from four different Oak Ridge tank farms will be immobilized. The sludges in these tanks contain transuranic radionuclides and RCRA metals at levels which will make the final waste from both TRU and mixed. The final waste form in the immobilization of these sludges may be glass because of its ability to accept a wide variety of components into its network structure. The results of these tests indicate that sufficient waste loadings can be obtained in the glass to significantly… more
Date: July 1, 1998
Creator: Andrews, M. K.; Workman, P. J.; Harbour, J. R. & Edwards, T. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fiscal year 1997 final report for task plan SR-16WT-31 task B, vitrification of ion exchange material

Description: In Fiscal Year 1997, the Department of Energy Tanks Focus Area (TFA) funded the Savannah River Technology Center (SRTC) to develop and demonstrate the vitrification of a CST ion exchange material loaded with radioactive cesium from one of the Melton Valley Storage Tanks at the Oak Ridge National Laboratory (ORNL). SRTC developed a patent-pending glass formulation that can be used to vitrify CST sorbent producing a quality borosilicate glass waste form. SRTC demonstrated this formulation by vitr… more
Date: September 30, 1997
Creator: Ferrara, D.; Andrews, M. K.; Harbour, J. R.; Fellinger, T. L.; Herman, D. T.; Marshall, K. M. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Vitrification of cesium-loaded crystalline silicotitanate (CST) in the shielded cells melter

Description: Through the Tanks Focus Area, the Savannah River Technology Center (SRTC) and the Oak Ridge National Laboratory participated in a joint project in which supernate waste from the Melton Valley Storage Tanks at Oak Ridge was treated by passage through a crystalline silicotitanate (CST) ion exchange column. CST was designed to sorb Cs- 137, Sr-90 and several other radionuclides from highly alkaline solutions containing large quantities of sodium.2 After demonstrating the effectiveness of CST as an… more
Date: September 30, 1997
Creator: Andrews, M. K.; Fellinger, T. L.; Ferrara, D. M.; Harbour, J. R. & Herman, D. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Glass formulation development and testing for the vitrification of DWPF HLW sludge coupled with crystalline silicotitanate (CST)

Description: An alternative to the In Tank Precipitation and sodium titanate processes at the Savannah River Site is the removal of cesium, strontium, and plutonium from the tank supernate by ion exchange using crystalline silicotitanate (CST). This inorganic material has been shown to effectively and selectively sorb these elements from supernate. The loaded CST could then be immobilized with High-Level Waste (HLW) sludge during vitrification. Initial efforts on the development of a glass formulation for a… more
Date: September 30, 1997
Creator: Andrews, M. K. & Workman, P. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Glass Waste Forms for Oak Ridge Tank Wastes: Fiscal Year 1997 Report for Task Plan SR-16WT-31, Task A

Description: Through the Tanks Focus Area, the Office of Science and Technology has funded the Savannah River Technology Center (SRTC) and the Oak Ridge National Laboratory (ORNL) to develop formulations which can incorporate sludges from Oak Ridge (OR) Tank Farms into an immobilized waste form. SRTC has been developing a glass waste form, while ORNL has been developing a grout waste form for the tank farms sludges. The four tank farms included in this task are: Melton Valley Storage Tanks (MVST), Bethel Va… more
Date: October 1, 1997
Creator: Andrews, M. K.; Harbour, J. R.; Edwards, T. B. & Workman, P. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Glass Formulation Development for the Vitrification of Oak Ridge Tank Waste

Description: Crystalline silicotitanate (CST) is a highly specific ion exchange material for cesium. In particular, CST has been successfully demonstrated with both simulants and actual supernates from Savannah River and Hanford tank wastes. As a disposal option, vitrification of the cesium-loaded CST coupled with High-Level Waste (HLW) has been proposed. However, the CST sorbent contains significant quantities of titanium which historically have been difficult to incorporate into the glass structure. There… more
Date: May 1, 1998
Creator: Andrews, M. K. & Workman, P. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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