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Book Multiple Ion Exchange Column Runs for Cesium and Technetium Removal from AW 101 Waste Sample

Download or read book Multiple Ion Exchange Column Runs for Cesium and Technetium Removal from AW 101 Waste Sample written by and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The River Protection Project -Waste Treatment Plant (RPP-WTP) will be performing cesium removal from Hanford tank waste supernatants using SuperLig 644 resin. These elutable resins will be used multiple times to process large volumes of radioactive waste samples and will be subjected to chemical and radiation degradation during use at the waste treatment plant (WTP). The RPP-WTP process design assumes that resin batches can be used a minimum of 10 cycles before the resin must be replaced due to degradation. The effects of radiation and chemical degradation on SuperLig 644 and 639 resins were separately studied in the past under static conditions, i.e., in contact with air, water, and simulated waste solutions. To determine the chemical degradation effects under dynamic or column conditions, Battelle, Pacific Northwest National Laboratory (PNNL), and IBC Advanced Technologies conducted multiple load/elute/regenerate cycles with simulated Hanford waste samples. Savannah River Technology Center (SRTC) was contracted to demonstrate the performance of SuperLig 644 and 639 resins to treat repetitively radioactive waste solutions. Six cycles of loading, elution, and regeneration were performed to remove cesium from a Hanford waste sample. Five load/elute/regenerate cycles were carried out to remove technetium from cesium-depleted effluent solutions. The multiple load/elute/regenerate cycles demonstrated that cesium and technetium can be effectively removed from a sample using SuperLig 644 and 639 resins. The percent cesium removal was greater than 99.99 per cent for each of the six cycles.

Book Multiple Ion Exchange Column Tests for Technetium Removal from Hanford Tank Waste Supernate

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.

Book Engineering Separations Unit Operations for Nuclear Processing

Download or read book Engineering Separations Unit Operations for Nuclear Processing written by Reid Peterson and published by CRC Press. This book was released on 2019-11-15 with total page 328 pages. Available in PDF, EPUB and Kindle. Book excerpt: Engineering Separations Unit Operations for Nuclear Processing provides insight into the fundamentals of separations in nuclear materials processing not covered in typical texts. This book integrates fuel cycle and waste processing into a single, coherent approach, demonstrating that the principles from one field can and should be applied to the other. It provides historical perspectives on nuclear materials processing, current assessment and challenges, and how past challenges were overcome. It also provides understanding of the engineering principles associated with handling nuclear materials. This book is aimed at researchers, graduate students, and professionals in the fields of chemical engineering, mechanical engineering, nuclear engineering, and materials engineering.

Book Tank Closure and Waste Management for the Hanford Site

Download or read book Tank Closure and Waste Management for the Hanford Site written by and published by . This book was released on 2012 with total page 1098 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Small Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241 AN 103

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 Comprehensive Scale Testing of the Ion Exchange Removal of Cesium and Technetium from Hanford Tank Wastes

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 Comparison of Organic and Inorganic Ion Exchangers for Removal of Cesium and Strontium from Simulated and Actual Hanford 241 AW 101 DSSF Tank Waste

Download or read book Comparison of Organic and Inorganic Ion Exchangers for Removal of Cesium and Strontium from Simulated and Actual Hanford 241 AW 101 DSSF Tank Waste written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A number of organic and inorganic exchangers are being developed and evaluated for cesium removal from Hanford tank wastes. The exchangers of interest that are investigated in this work include powdered (IONSIV[reg-sign] IE-910; referred to as IE-910) and engineered (IONSIV[reg-sign] IE-911; referred to as IE-911) forms of the crystalline silico-titanate (CST) inorganic sorbent developed by Sandia National Laboratories (SNL)/Texas A and M and prepared by UOP; a phenol-formaldehyde (CS-100) resin developed by Rohm and Haas; a resorcinol-formaldehyde (R-F) polymer developed at the Westinghouse Savannah River Company (WSRC) and produced by Boulder Scientific; an inorganic zeolite exchanger produced by UOP (IONSIV[reg-sign] TIE-96; referred to as TIE-96); an inorganic sodium titanate produced by Allied Signal/Texas A and M (NaTi); and a macrocyclic organic resin developed and produced by IBC Advanced Technologies (SuperLig[reg-sign] 644; referred to as SL-644). Several of these materials are still under development and may not be in the optimal form. The work described in this report involves the direct comparison of the ion exchange materials for the pretreatment of actual and simulated Hanford tank waste. Data on the performance of all of the exchangers with simulated and actual double shell slurry feed (DSSF) is included. The DSSF waste is a mixture of the supernate from tanks 101-AW (70%), 106-AP (20%) and 102-AP (10%). The comparative parameters include radionuclide removal efficiency under a variety of conditions and material properties (e.g., bed density and percent removable water). Cesium and strontium distribution (K[sub d]), lambda ([lambda]= K[sub d][times][rho][sub b]), and decontamination factors (DF) are compared as a function of exchanger contact duration, solution composition (Na and Cs concentration), exchanger/waste phase ratio, and multiple sequential contacts.

Book Ion Exchange Recovery of Cesium from Alkaline Supernatant Waste

Download or read book Ion Exchange Recovery of Cesium from Alkaline Supernatant Waste written by R. P. Popovich and published by . This book was released on 1964 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Ion Exchange Columns for Selective Removal of Cesium from Aqueous Radioactive Waste Using Hydrous Crystalline Silico titanates

Download or read book Ion Exchange Columns for Selective Removal of Cesium from Aqueous Radioactive Waste Using Hydrous Crystalline Silico titanates written by David Michael Ricci and published by . This book was released on 1995 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Cesium Ion Exchange Using Actual Waste

Download or read book Cesium Ion Exchange Using Actual Waste written by Kriston P. Brooks and published by . This book was released on 1996 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Small Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241 AN 102

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 Intermediate Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241 AN 102

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 Cesium Ion Exchange Using Tank 241 AN 104 Supernate

Download or read book Cesium Ion Exchange Using Tank 241 AN 104 Supernate written by K. Adu-Wusu and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The River Protection Project is to design and build a high level nuclear waste treatment facility. The waste treatment plant is to process millions of gallons of radioactive waste stored in tanks at the Hanford Site. The high level nuclear waste treatment process includes various unit operations, such as ultrafiltration, precipitation, evaporation, ion exchange, and vitrification. Ion exchange is identified as the optimal treatment method for removal of cesium-137 and Tc-99 from the waste. Extensive ion exchange testing was performed using small-scale columns with actual waste samples. The objectives of this study were to: demonstrate SuperLig 644 ion exchange performance and process steps for the removal of cesium from actual AN-104 tank waste; pretreat actual AN-104 tank waste to reduce the concentration of cesium-137 in the waste below LAW vitrification limit; produce and characterize cesium eluate solutions for use in eluate evaporation tests. The experiments consisted of batch contact and small-scale column tests. The batch contact tests measured sorption partition coefficients Kds. The Kds were used to predict the effective resin capacity. The small-scale column tests, which closely mimic plant conditions, generated loading and elution profile data used to determine whether removal targets and design requirements were met.

Book Ion Exchange Modeling of Crystalline Silicotitanate  IONSIV R  IE 911  Column for Cesium Removal from Argentine Waste

Download or read book Ion Exchange Modeling of Crystalline Silicotitanate IONSIV R IE 911 Column for Cesium Removal from Argentine Waste written by and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. Department of Energy (DOE) and the Nuclear Energy Commission of Argentina (CNEA) have a collaborative project to separate cesium/strontium from waste resulting from the production of Mo-99. The Pacific Northwest National Laboratory (PNNL) is assisting DOE on this joint project by providing technical guidance to CNEA scientists. As part of the collaboration, PNNL staff works with staff at the Savannah River Technology Center (SRTC) to run the VERSE-LC model for removal of cesium from the Mo-99 waste using the crystalline silicotitanate (CST) material (IONSIV(R) IE-911, UOP LLC, DesPlaines, IL) based on technical data provided by CNEA. This report discusses the VERSE-LC ion-exchange-column model and the predicted results of CNEA test cases.

Book Preliminary Ion Exchange Modeling for Removal of Cesium from Hanford Waste Using SuperLig 644 Resin

Download or read book Preliminary Ion Exchange Modeling for Removal of Cesium from Hanford Waste Using SuperLig 644 Resin written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: A proposed facility is being designed for the immobilization of Hanford high-level radioactive waste. One unit process in the facility is designed to remove radioactive cesium by ion-exchange from the strongly alkaline aqueous phase. A resin specifically designed with high selectivity of cesium under alkaline conditions is being investigated. The resin also is elutable under more acidic conditions. The proposed design of the facility consists of two sets of two packed columns placed in series (i.e., a lead column followed by a lag (guard) column configuration). During operation, upon reaching a specified cesium concentration criterion at the exit of the lag column, operation is switched to the second set of lead and lag columns. The cesium-loaded lead column is processed (i.e., washed and eluted) and switched to the lag position. the previous lag column is then placed in the lead position (without eluting) and the system is ready for use in the next cycle. For a well designed process, the loading and elution processes result in significant volume reductions in aqueous high-level waste.

Book Technetium Removal Column Flow Testing with Alkaline  High Salt  Radioactive Tank Waste

Download or read book Technetium Removal Column Flow Testing with Alkaline High Salt Radioactive Tank Waste written by David L. Blanchard (Jr.) and published by . This book was released on 1996 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: