SPEEDUP Simulation of Liquid Waste Batch Processing. Revision 1

SPEEDUP Simulation of Liquid Waste Batch Processing. Revision 1

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Published: 1994

Total Pages: 44

ISBN-13:

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The Savannah River Site (SRS) has accumulated radioactive hazardous waste for over 40 years during the time SRS made nuclear materials for the United States Department of Energy (DOE) and its predecessors. This waste is being stored as caustic slurry in a large number of 1 million gallon steel tanks, some of which were initially constructed in the early 1950's. SRS and DOE intend to clean up the Site and convert this waste into stable forms which then can be safely stored. The liquid waste will be separated into a partially decontaminated low-level and radioactive high-level waste in one feed preparation operation, In-Tank Precipitation. The low-level waste will be used to make a concrete product called saltstone in the Saltstone Facility, a part of the Defense Waste Processing Facility (DWPF). The concrete will be poured into large vaults, where it will be permanently stored. The high-level waste will be added to glass-formers and waste slurry solids from another feed preparation operation, Extended Sludge Processing. The mixture will then be converted to a stable borosilicate glass by a vitrification process that is the other major part of the DWPF. This glass will be poured into stainless steel canisters and sent to a temporary storage facility prior to delivery to a permanent underground storage site.


Feed Acceptance for the Defense Waste Processing Facility at the Savannah River Site

Feed Acceptance for the Defense Waste Processing Facility at the Savannah River Site

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Published: 1998

Total Pages: 28

ISBN-13:

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The DWPF at the Department of Energy's (DOE) Savannah River Site (SRS) began radioactive operations in December of 1995. The High Level Waste Tank Farm at SRS contains approximately thirty three million gallons of salt, supernate, and insoluble sludge wastes accumulated during more than three decades of weapons manufacture. In the DWPF, the radioactive components from this waste will ultimately be processed into a stable, borosilicate glass for long-term storage in a geological repository. The feeds to the DWPF are pretreated in a number of steps. Insoluble sludges, primarily aluminum, iron and other transition metals, are combined from several tanks, treated by caustic dissolution of aluminum and washed to remove soluble salts; these materials are removed to increase waste loading in the glass produced by the DWPF. The water soluble radioactive species in the salt and supernate, primarily cesium and actinides, are precipitated by sodium tetraphenylborate (NaTPB) or adsorbed onto sodium titanate. The resulting solids are also washed to remove excessive soluble salts before feeding to the DWPF. The soluble species removed by washing are disposed of as low level radioactive waste in a concrete form known as Saltstone. The presentation includes a brief overview of the High Level Waste system, pretreatment, and disposition of the various streams. The washed tetraphenylborate precipitates of cesium and potassium are hydrolyzed by copper catalyzed formic acid hydrolysis in the Salt Processing Cell (SPC) to yield soluble formates, boric acid, benzene and minor organic byproducts. The benzene and most of the organic byproducts are then steam stripped. The resulting aqueous hydrolysis product, including the still insoluble actinides adsorbed onto sodium titanate, is combined in the Chemical Processing Cell (CPC) with the insoluble sludge which has been treated with nitric acid and formic acid to remove mercury and to adjust the glass redox. Borosilicate glass frit is added and after assuring the melter feed meets glass quality and processing requirements, the slurry is fed to the melter producing glass which is poured into stainless steel canisters. The canisters are sealed, blasted to remove surface contamination, and welded prior to temporary storage in the Glass Waste Storage Building (GWSB). An overview of the DWPF process and its chemistry is included. The composition of the feeds is of primary importance to the DWPF. Critical factors determined by the feeds are related to safety, process design and operability, and glass quality. The Safety Analysis Report (SAR) source term, process shielding, potential for criticality, and generation of flammable gases are safety factors related to feed composition. Canister heat generation, NO(subscript x) emissions, and corrosive species are process design parameters determined by feed composition. Nitrite in the washed precipitate, glass insolubles, glass liquidus (temperature of complete melting) and glass melt viscosity are operability parameters determined by composition. And glass durability is the critical quality parameter which requires knowledge and control of the feed compositions. The basis for each of these composition related factors is presented and the system for specifying feed acceptance criteria is described. The composition, and thus the durability, of the glass is determined by the mixing ratios of sludge insolubles, aqueous hydrolysis product, and frit. The frit is a purchased raw material; naturally, its composition is essentially fixed. Also, the glass components in the aqueous hydrolysis product are essentially invariant because the cesium plus potassium to boron ratio is unity, essentially all of the water is evaporated, and the sodium titanate concentration is carefully controlled in the precipitation process. Therefore, the sludge composition is the primary source of feed variability. The combination of process and tank farm history, strategic tank samples, system waste removal plans, and process modeling which project sludge batch composition and evaluate process related parameters and glass durability is described. All the sludge batches, each of which can feed the DWPF for several years, is projected and evaluated through completion of waste removal. Finally, extensive sludge characterization through sampling and analysis is combined with small scale testing in the Shielded Cells of the Savannah River Technology Center (SRTC) to assure the sludge batch meets all the feed acceptance criteria.


Control of DWPF (Defense Waste Processing Facility) Melter Feed Composition

Control of DWPF (Defense Waste Processing Facility) Melter Feed Composition

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Published: 1990

Total Pages: 9

ISBN-13:

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The Defense Waste Processing Facility will be used to immobilize Savannah River Site high-level waste into a stable borosilicate glass for disposal in a geologic repository. Proper control of the melter feed composition in this facility is essential to the production of glass which meets product durability constraints dictated by repository regulations and facility processing constraints dictated by melter design. A technique has been developed which utilizes glass property models to determine acceptable processing regions based on the multiple constraints imposed on the glass product and to display these regions graphically. This system along with the batch simulation of the process is being used to form the basis for the statistical process control system for the facility. 13 refs., 3 figs., 1 tab.


DWPF Batch 1, Waste Glass Investigations

DWPF Batch 1, Waste Glass Investigations

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Published: 1991

Total Pages: 12

ISBN-13:

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The initial feed to the Defense Waste Processing Facility at the Savannah River Site is currently being prepared and characterized. In the DWPF, this material will be mixed with glass frit and vitrified. The goal of this study is to investigate the effects of variability in the feed mixture on important glass properties. The results will be used to validate the composition -- property models which will be used for process control.


Advances in Materials Science for Environmental and Nuclear Technology II

Advances in Materials Science for Environmental and Nuclear Technology II

Author: S. K. Sundaram

Publisher: John Wiley & Sons

Published: 2011-07-12

Total Pages: 350

ISBN-13: 1118060008

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This book contains 29 papers from the Clean Energy: Fuel Cells, Batteries, Renewables; Green Technologies for Materials Manufacturing and Processing II; and Materials Solutions for the Nuclear Renaissance symposia held during the 2010 Materials Science and Technology (MS&T'10) meeting, October 17-21, 2010, Houston, Texas. Topics include Batteries; Corrosion and Materials Degradation; Fuel Cells & Electrochemistry; Fossil Energy Materials; Solar Energy; Waste Minimization; Green Manufacturing and Materials Processing; Immobilization of Nuclear Wastes; Irradiation and Corrosion Effects; and Materials Performance in Extreme Environments.