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Intermediate Scale Ion Exchange Removal Of Technetium From Savannah River Site Tank 44 F Supernate Solution
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Book Synopsis Intermediate-Scale Ion Exchange Removal of Technetium from Savannah River Site Tank 44 F Supernate Solution by :
Download or read book Intermediate-Scale Ion Exchange Removal of Technetium from Savannah River Site Tank 44 F Supernate Solution written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of the Hanford River Protection Project waste Treatment facility design contracted to BNFL, Inc., a sample of Savannah River Site (SRS) Tank 4 F waste solution was treated for the removal of technetium (as pertechnetate ion). Interest in treating the SRS sample for Tc removal resulted from the similarity between the Tank 44 F supernate composition and Hanford Envelope A supernate solutions. The Tank 44 F sample was available as a by-product of tests already conducted at the Savannah River Technology Center (SRTC) as part of the Alternative Salt Disposition Program for treatment of SRS wastes. Testing of the SRS sample resulted in considerable cost-savings since it was not necessary to ship a sample of Hanford supernate to SRS.
Book Synopsis Intermediate-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102 by :
Download or read book Intermediate-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102 written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Ion exchange tests have been completed at the Savannah River Technology Center for British Nuclear Fuels Limited, Inc. as part of the Hanford River Protection Project. Radioactive cesium and technetium (pertechnetate form only) were removed by ion exchange from a sample of Envelope C salt solution from Hanford Tank 241-AN-102 (sample volume: approximately 17 L at 4.8 M Na plus). The original sample was diluted and subjected to strontium/transuranics (Sr/TRU) precipitation and filtration processes before ion exchange processing was performed. Batch contact and column tests for the ion exchange removal of cesium and technetium were then completed on the Sr/TRU-decontaminated product. Previous ion exchange tests were conducted on a smaller portion (0.5 L) of the Tank 241-AN-102 supernate sample, which had been similarly pretreated, and the results were reported in a separate document.
Book Synopsis Small-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-103 by :
Download or read book Small-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-103 written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The pretreatment process for BNFL, Inc.'s Hanford River Protection Project is to provide decontaminated low activity waste and concentrated eluate streams for vitrification into low activity and high level waste glass, respectively. The pretreatment includes sludge washing, filtration, precipitation, and ion exchange processes to remove entrained solids, cesium, transuranics, technetium, and strontium. The ion exchange removal of cesium (Cs) and technetium (Tc) ions is accomplished by using SuperLig 644, and 639 resins from IBC Advanced Technologies, American Fork, Utah. The resins were shown to selectively remove cesium and technetium (as pertechnetate), from alkaline salt solutions. The efficiency of ion exchange column loading and elution is a complex function involving feed compositions, equilibrium and kinetic behavior of ion exchange resins, diffusion, and the ionic strength and pH of the aqueous solution. A previous experimental program completed at the Savannah River Technology Center demonstrated the conceptualized flow sheet parameters with a similar Hanford tank sample (241-AW-101). Those experiments included determination of Cs and Tc batch distribution coefficients by SuperLig 644 and 639 resins and demonstration of small-scale column breakthrough and elution. The experimental findings were used in support of preliminary design bases and pretreatment flow sheet development by BNFL, Inc.
Book Synopsis Small-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102 by :
Download or read book Small-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102 written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The pretreatment process for BNFL, Inc.'s Hanford River Protection Project is to provide decontaminated low activity waste and concentrated eluate streams for vitrification into low and high activity waste glass, respectively. The pretreatment includes sludge washing, filtration, precipitation, and ion exchange processes to remove entrained solids, cesium, transuranics, technetium, and strontium. The cesium (Cs-137) and technetium (Tc-99) ion exchange removal is accomplished by using SuperLig 644, and 639 resins from IBC Advanced Technologies, American Fork, Utah. The resins were shown to selectively remove cesium and technetium (as anionic pertechnetate) from alkaline salt solutions. The efficiency of ion exchange column loading and elution is a complex function involving feed compositions, equilibrium and kinetic behavior of ion exchange resins, diffusion, and the ionic strength and pH of the aqueous solution. A previous experimental program completed at the Savannah River Tech nology Center2 demonstrated the conceptualized flow sheet parameters with an Envelope C sample from Hanford Tank 241-AN-107. Those experiments also included determination of Cs and Tc batch distribution coefficients by SuperLig 644 and 639 resins and demonstration of small-scale column breakthrough and elution. The experimental findings were used in support of preliminary design bases and pretreatment flow sheet development by BNFL, Inc.
Book Synopsis Technetium Removal from Hanford and Savannah River Site Actual Tank Waste Supernates with SuperLig(R) 639 Resin by :
Download or read book Technetium Removal from Hanford and Savannah River Site Actual Tank Waste Supernates with SuperLig(R) 639 Resin written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: SuperLig(R) 639 elutable, organic resin has been selected for technetium (as pertechnetate ion) removal from Hanford Site radioactive waste samples as part of the River Protection Project - Waste Treatment Plant (RPP-WTP) design. In support of the RPP-WTP flow sheet development, column tests have been performed at the Savannah River Technology Center with SuperLig(R) 639 resin using actual Hanford Site tank waste samples. The resin was shown to be highly effective at pertechnetate removal from these caustic, high-sodium, aqueous waste samples. Pertechnetate ion was subsequently eluted from the columns with water. An additional column test conducted on a Savannah River Site waste sample revealed exceptional performance, presumably due to the fact that lower concentrations of competing anions (primarily nitrate) were present in the sample.
Book Synopsis Multiple Ion Exchange Column Tests for Technetium Removal from Hanford Tank Waste Supernate by :
Download or read book Multiple Ion Exchange Column Tests for Technetium Removal from Hanford Tank Waste Supernate written by and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Five cycles of loading, elution, and regeneration were performed to remove technetium from a Hanford waste sample retrieved from Tank 241-AW-101 using SuperLig 639 resin. The waste sample was diluted to 4.95 M Na plus and then was processed to remove 137Cs through dual ion exchange columns each containing 15 mL of SuperLig 644. To remove 99Tc, the cesium decontaminated solution was processed downwards through two ion exchange columns, each containing 12 mL of SuperLig 639 resin. The columns, designated as lead and lag, each had an inside diameter of 1.45 cm and a height of 30 cm. The columns were loaded in series, but were eluted and then regenerated separately. The average technetium loading for the cycles was 250 BV at 10 percent breakthrough. There was no significant difference in the loading performances among the five cycles. The percent removal of 99Tc was greater than 99.94 percent and the average decontamination factor (DF) was approximately 1.7 x 103. Approximately 99 percent of the 99Tc loaded on the resin was eluted with less than 15 BV of de-ionized water at 65 degrees C.
Download or read book אגרות י"שור written by and published by . This book was released on 1899 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis In Situ Removal of Actinides and Strontium from High Level Waste Tanks, Tea Bag Versus Adsorption Column by : CROWDER. MARK
Download or read book In Situ Removal of Actinides and Strontium from High Level Waste Tanks, Tea Bag Versus Adsorption Column written by CROWDER. MARK and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Initiatives are underway at the Savannah River Site (SRS) to accelerate the disposition of the supernate and salt portions of the waste in the SRS High Level Waste (HLW) tank farm system. Significant savings in processing time and overall cost could be achieved by in situ treatment of waste supernate or dissolved salt inside a tank farm waste tank. For treatment of actinides and strontium in waste, the baseline method is sorption onto monosodium titanate (MST), an engineered powder with mean particle size of approximately 10 microns. In a separate study at the Savannah River National Laboratory (SRNL), engineered forms of MST were developed and compared on a small (250-mL) scale in batch tests. In the current study, a promising form of engineered MST was tested under two conditions: a traditional ion exchange (or adsorption) column and a porous, flow through device called a tea bag, immersed in solution. Both tests used the same amount of engineered MST to treat 10 L of simulated waste solution containing plutonium and strontium.
Book Synopsis Comprehensive Scale Testing of the Ion Exchange Removal of Cesium and Technetium from Hanford Tank Wastes by :
Download or read book Comprehensive Scale Testing of the Ion Exchange Removal of Cesium and Technetium from Hanford Tank Wastes written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Highly selective ion exchange materials will be used to remove radionuclides from tank waste at the Hanford site as part of the River Protection Project. Testing in support of facility design was performed with different sizes of ion exchange columns to provide a basis for comparing results obtained using small-scale with radioactive samples and full design-height (i.e., pilot-scale) with simulant. Results indicate good comparison between small-scale radioactive tests and pilot-scale simulant tests. Because of the cost of performing radioactive tests and the unavailability of large sample volumes, understanding scale-up of performance parameters is critical to ensure that the system will perform as designed. The consistency of scale-up of ion exchange columns using SuperLig 644 and 639 resins has been demonstrated. Maintaining constant residence time, i.e., Column Volumes per hour, yields similar breakthrough profiles with resin columns ranging from 3.5 cm to 230 cm in height. Experiments performed with flow rates greatly exceeding the design parameters provided valuable information on loading and diffusion parameters. These data will be used, along with a computer model, to permit verification of design and prediction of column performance.
Book Synopsis Tank 241-AZ-102 SuperLig 639 Technetium Ion Exchange Eluate Evaporation Study by :
Download or read book Tank 241-AZ-102 SuperLig 639 Technetium Ion Exchange Eluate Evaporation Study written by and published by . This book was released on 2001 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of the Hanford River Protection Project (RPP), the Savannah River Technology Center (SRTC) has conducted tests on the pretreatment and vitrification of a radioactive waste sample from Hanford Tank 241-AZ-102. The original, AZ-102 sample which was received at SRTC was characterized and filtered to remove entrained solids. 1 The sample was then passed sequentially through ion exchange columns containing SuperLig{reg_sign} 644 and 639 resins for the removal of cesium and technetium ions (Tc removed as pertechnetate, TcO4−), respectively. 2 The cesium and technetium absorbed to the resins was then eluted to give separate eluate solutions containing relatively high concentrations of Cs and TcO4−. According to the current plant design, the decontaminated Tank 241-AZ-102 sample and the eluate solutions will be subjected to separate evaporation and vitrification processes to give low- and high-activity waste glasses, respectively. This report describes evaporation testing of the Tc eluate solution derived from ion exchange processing of the Tank 241-AZ-102 sample with SuperLig 639 resin.
Book Synopsis Decontamination of Savannah River Waste Supernate by Ion Exchange by : H. Katz
Download or read book Decontamination of Savannah River Waste Supernate by Ion Exchange written by H. Katz and published by . This book was released on 1964 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis REMOVAL OF TECHNETIUM 99 FROM THE EFFLUENT TREATMENT FACILITY (ETF) BASIN 44 USING PUROLITE A-530E & REILLEX HPQ & SYBRON IONAC SR-7 ION EXCHANGE RESINS. by : DUNCAN JB.
Download or read book REMOVAL OF TECHNETIUM 99 FROM THE EFFLUENT TREATMENT FACILITY (ETF) BASIN 44 USING PUROLITE A-530E & REILLEX HPQ & SYBRON IONAC SR-7 ION EXCHANGE RESINS. written by DUNCAN JB. and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report documents the laboratory testing and analyses as directed under the test plan, RPP-20407. The overall goal of this task was to evaluate and compare candidate anion exchange resins for their capacity to remove Technetium-99 from Basin 44 Reverse Osmosis reject stream. The candidate resins evaluated were Purolite A-530E, Reillex HPQ, and Sybron IONAC SR-7.
Book Synopsis Permanganate Reduction of Savannah River Site Actual Waste Samples for Strontium and Actinides Removal by :
Download or read book Permanganate Reduction of Savannah River Site Actual Waste Samples for Strontium and Actinides Removal written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The authors investigated the performance of permanganate treatment for the removal of strontium and actinides from actual high-level waste. Researchers also conducted comparison tests with monosodium titanate (MST) as a means of evaluating the permanganate performance. Tests utilized a Tank 37H/44F composite waste solution. Personnel significantly increased the concentration of alpha emitting actinides in the waste by the addition of acidic americium/curium solution (F-Canyon Tank 17.1 solution), which contained a significant quantity of plutonium, and neptunium-237 stock solution. Tests examined three permanganate treatment options.
Book Synopsis Reengineering Water Treatment Units for Removal of Sr-90, I-129, Tc-99, and Uranium from Contaminated Groundwater at the DOE's Savannah River Site by :
Download or read book Reengineering Water Treatment Units for Removal of Sr-90, I-129, Tc-99, and Uranium from Contaminated Groundwater at the DOE's Savannah River Site written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The 33 years of active operation of the F- and H-Area Seepage Basins to dispose of liquid low-level radioactive waste at the Department of Energy's Savannah River Site has resulted in the contamination of the groundwater underlying these basins with a wide variety of radionuclides and stable metals. The current Resource Conservation and Recovery Act (RCRA) Part B permit requires the operation of a pump-and-treat system capable of (1) maintaining hydraulic control of a specified contaminated groundwater plume, (2) treatment of the extracted groundwater, and (3) reinjection of the treated water hydraulically upgradient of the basins. Two multimillion-dollar water treatment units (WTUs) were designed and built in 1997 and the basic design consists of (1) reverse osmosis concentration, (2) chemical addition, neutralization, precipitation, polymer addition, flocculation, and clarification of the reverse osmosis concentrate, and (3) final polishing of the clarified water by ion exchange (IX) and sorption. During startup of these units numerous process optimizations were identified and, therefore, the WTUs have been recently reengineered. A systematic approach of: (1) developing a technical baseline through laboratory studies, (2) scale-up and plant testing, (3) plant modification, and (4) system performance monitoring was the basis for reengineering the WTUs. Laboratory experiments were conducted in order to establish a technical baseline for further scale-up/plant testing and system modifications. These studies focused on the following three areas of the process: (1) contaminant removal during chemical addition, neutralization and precipitation, (2) solids separation by flocculation, coagulation, clarification, and filtration, and (3) contaminant polishing of the clarified liquid by IX/sorption. Using standard laboratory-scale jar tests, the influences of pH and Fe concentration on contaminant removal during precipitation/neutralization were evaluated. The results of this work led to plant testing and operation modification that reduced the chemical dosing by a factor of 2 to 4 for one WTU and complete elimination of chemical addition at the other WTU. The solids separation process was also reengineered through polymer-dose optimization and plant modifications to control the mixing intensity and flocculation reaction time. The results were enhanced floc quality (floc size, settling rate, sludge volume, supernatant turbidity) at a polymer dose of one-half historical levels. IX/sorption optimization was initiated by evaluating 14 different IX/sorbent materials for their ability to remove specific nuclides in a series of column experiments. Analysis of time-dependent effluent activity/concentration data was used to determine the contaminant breakthrough and identify alternative resins for plant testing. Significant plant modifications, including the replacement of the natural zeolite with a commercial water softening IX resin that is one-third the cost and has twice the operational life for 90Sr removal, were made to both WTUs. The result of this reengineering has been enhanced contaminant removal, dramatically increased system reliability, lower operational costs, reduced secondary waste volume, and decreased personnel exposure. The specifics of this reengineering process and the associated system changes are presented in this paper.
Book Synopsis Vitrification of Ion Exchange Materials. Innovative Technology Summary Report by :
Download or read book Vitrification of Ion Exchange Materials. Innovative Technology Summary Report written by and published by . This book was released on 1999 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: Ion exchange is a process that safely and efficiently removes radionuclides from tank waste. Cesium and strontium account for a large portion of the radioactivity in waste streams from US Department of Energy (DOE) weapons production. Crystalline silicotitanate (CST) is an inorganic sorbent that strongly binds cesium, strontium, and several other radionuclides. Developed jointly by Sandia National Laboratory and Texas A and M University, CST was commercialized through a cooperative research and development agreement with an industrial partner. Both an engineered (mesh pellets) and powdered forms are commercially available. Cesium removal is a baseline in HLW treatment processing. CST is very effective at removing cesium from HLW streams and is being considered for adoption at several sites. However, CST is nonregenerable, and it presents a significant secondary waste problem. Treatment options include vitrification of the CST, vitrification of the CST coupled with HLW, direct disposal, and low-temperature processes such as grouting. The work presented in this report demonstrates that it is effective to immobilize CST using a baseline technology such as vitrification. Vitrification produces a durable waste form. CST vitrification was not demonstrated before 1996. In FY97, acceptable glass formulations were developed using cesium-loaded CST obtained from treating supernatants from Oak Ridge Reservation (ORR) tanks, and the CST was vitrified in a research melter at the Savannah River Technology Center (SRTC). In FY98, SRS decided to reevaluate the use of in-tank precipitation using tetraphenylborate to remove cesium from tank supernatant and to consider other options for cesium removal, including CST. Hanford and Idaho National Engineering and Environmental Laboratory also require radionuclide removal in their baseline flowsheets.
Book Synopsis Pilot Scale Testing of Monosodium Titanate Mixing for the SRS Small Column Ion Exchange Process - 11224 by :
Download or read book Pilot Scale Testing of Monosodium Titanate Mixing for the SRS Small Column Ion Exchange Process - 11224 written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and select actinides from Savannah River Site (SRS) Liquid Waste using an existing waste tank (i.e., Tank 41H) to house the process. Savannah River National Laboratory (SRNL) is conducting pilot-scale mixing tests to determine the pump requirements for suspending monosodium titanate (MST), crystalline silicotitanate (CST), and simulated sludge. The purpose of this pilot scale testing is to determine the requirements for the pumps to suspend the MST particles so that they can contact the strontium and actinides in the liquid and be removed from the tank. The pilot-scale tank is a 1/10.85 linear scaled model of SRS Tank 41H. The tank diameter, tank liquid level, pump nozzle diameter, pump elevation, and cooling coil diameter are all 1/10.85 of their dimensions in Tank 41H. The pump locations correspond to the proposed locations in Tank 41H by the SCIX program (Risers B5 and B2 for two pump configurations and Risers B5, B3, and B1 for three pump configurations). The conclusions from this work follow: (i) Neither two standard slurry pumps nor two quad volute slurry pumps will provide sufficient power to initially suspend MST in an SRS waste tank. (ii) Two Submersible Mixer Pumps (SMPs) will provide sufficient power to initially suspend MST in an SRS waste tank. However, the testing shows the required pump discharge velocity is close to the maximum discharge velocity of the pump (within 12%). (iii) Three SMPs will provide sufficient power to initially suspend MST in an SRS waste tank. The testing shows the required pump discharge velocity is 66% of the maximum discharge velocity of the pump. (iv) Three SMPs are needed to resuspend MST that has settled in a waste tank at nominal 45 C for four weeks. The testing shows the required pump discharge velocity is 77% of the maximum discharge velocity of the pump. Two SMPs are not sufficient to resuspend MST that settled under these conditions.
Book Synopsis An Evaluation of an Ion-exchange Method for the Removal of Technetium-99 from Groundwater by : Wanda Sue Elliott
Download or read book An Evaluation of an Ion-exchange Method for the Removal of Technetium-99 from Groundwater written by Wanda Sue Elliott and published by . This book was released on 2007 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
