Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Strontium And Actinide Removal Testing With Monosodium Titanate And Other Sorbents
Download Strontium And Actinide Removal Testing With Monosodium Titanate And Other Sorbents full books in PDF, epub, and Kindle. Read online Strontium And Actinide Removal Testing With Monosodium Titanate And Other Sorbents ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Strontium and Actinide Removal Testing with Monosodium Titanate and Other Sorbents by :
Download or read book Strontium and Actinide Removal Testing with Monosodium Titanate and Other Sorbents written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: SRTC researchers examined the affects of solution phase composition, the oxidation state of plutonium and neptunium and different production batches on the performance of monosodium titanate (MST) to remove strontium and actinides from alkaline salt solutions. Testing also evaluated the performance of alternate sorbents including sodium nonatitanate (ST), crystalline silicotitanate and pharamacosiderite materials.
Book Synopsis TAILORING INORGANIC SORBENTS FOR SRS STRONTIUM AND ACTINIDE SEPARATIONS by :
Download or read book TAILORING INORGANIC SORBENTS FOR SRS STRONTIUM AND ACTINIDE SEPARATIONS written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This document provides a final report of Phase III testing activities for the development of modified monosodium titanate (mMST), which exhibits improved strontium and actinide removal characteristics compared to the baseline MST material. The activities included characterization of the crystalline phases present at varying temperatures, solids settling characteristics, quantification of the peroxide content; evaluation of the post-synthesis gas release under different conditions; the extent of desorption of 85Sr, Np, and Pu under washing conditions; and the effects of age and radiation on the performance of the mMST. Key findings and conclusions include the following. The peroxide content of several mMST samples was determined using iodometric titration. The peroxide content was found to decrease with age or upon extended exposure to elevated temperature. A loss of peroxide was also measured after exposure of the material to an alkaline salt solution similar in composition to the simulated waste solution. To determine if the loss of peroxide with age affects the performance of the material, Sr and actinide removal tests were conducted with samples of varying age. The oldest sample (4 years and 8 months) did show lower Sr and Pu removal performance. When compared to the youngest sample tested (1 month), the oldest sample retained only 15% of the DF for Pu. Previous testing with this sample indicated no decrease in Pu removal performance up to an age of 30 months. No loss in Np removal performance was observed for any of the aged samples, and no uptake of uranium occurred at the typical sorbent loading of 0.2 g/L. Additional testing with a uranium only simulant and higher mMST loading (3.0 g/L) indicated a 10% increase of uranium uptake for a sample aged 3 years and 8 months when compared to the results of the same sample measured at an age of 1 year and 5 months. Performance testing with both baseline-MST and mMST that had been irradiated in a gamma source to a total dose of 3.95 x 106 R, indicated little to no affect on the performance of the material to remove Sr and actinides. Previous testing established that mMST releases oxygen gas during the synthesis, and continues to off-gas during storage post synthesis. The post-synthesis gas release rate was measured under several conditions, including varying the pH of the wash water and at elevated temperature (49 C, typical of bounding summertime storage without air conditioning). Results indicated that a high pH (basic) wash reduced the initial gas release rate, but after 2 days the release rates from all different pH washed samples were not statistically different. The gas release rate at 49 C, a temperature at which the material may be exposed to during shipping and storage, was consistently about 2.5 times higher than the rate at room temperature. All gas release results indicated that vented containers would be necessary for shipping and storage of large quantities of material. Suspension of sorbate-loaded solids into diluted solutions representing intermediate and final stages of washing for 24-hours revealed no evidence of desorption of Sr, Pu or Np from the mMST solids. Based on the results of the Phase III testing as well as that from earlier studies (Phases I and II), SRNL researchers recommend adopting the use of the mMST material for the removal of strontium and actinides from the SRS HLW supernatant liquids in the Actinide Removal Process and Salt Waste Processing Facility. Given the decrease in Sr and Pu removal performance for the mMST having an age of 4 years and 8 months, we recommend that mMST be used within 30 months of production. Furthermore we recommend that DOE provide funding to conduct pilot-scale testing of the mixing and settling characteristics of the mMST and impact, if any, on the generation of hydrogen during processing in the Defense Waste Processing Facility (DWPF).
Book Synopsis TAILORING INORGANIC SORBENTS FOR SRS STRONTIUM AND ACTINIDE SEPARATIONS by : D. Hobbs
Download or read book TAILORING INORGANIC SORBENTS FOR SRS STRONTIUM AND ACTINIDE SEPARATIONS written by D. Hobbs and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This document provides an interim summary report of Phase II testing activities for the development of a modified monosodium titanate (MST) that exhibits improved strontium and actinide removal characteristics compared to the baseline MST materials. The activities included determining the key synthesis conditions for preparation of the modified MST, preparation of the modified MST at a larger laboratory scale, demonstration of the strontium and actinide removal characteristics with actual tank waste supernate and characterization of the modified MST. Key findings and conclusions include the following: (1) Samples of the modified MST prepared by Method 2 and Method 3 exhibited the best combination of strontium and actinide removal. (2) We selected Method 3 to scale up and test performance with actual waste solution. (3) We successfully prepared three batches of the modified MST using the Method 3 procedure at a 25-gram scale. (4) Performance tests indicated successful scale-up to the 25-gram scale with excellent performance and reproducibility among each of the three batches. For example, the plutonium decontamination factors (6-hour contact time) for the modified MST samples averaged 13 times higher than that of the baseline MST sample at half the sorbent concentration (0.2 g L{sup -1} for modified MST versus 0.4 g L{sup -1} for baseline MST). (5) Performance tests with actual waste supernate demonstrated that the modified MST exhibited better strontium and plutonium removal performance than that of the baseline MST. For example, the decontamination factors for the modified MST measured 2.6 times higher for strontium and between 5.2 to 11 times higher for plutonium compared to the baseline MST sample. The modified MST did not exhibit improved neptunium removal performance over that of the baseline MST. (6) Two strikes of the modified MST provided increased removal of strontium and actinides from actual waste compared to a single strike. The improved performance exhibited by the modified MST indicates that fewer strikes of the modified MST would be needed to successfully treat waste that contain very high activities of {sup 90}Sr and alpha-emitting radionuclides compared to the baseline MST. (7) Reuse tests with actual waste confirmed that partially loaded MST exhibits reduced removal of strontium and actinides when contacted with fresh waste. (8) Samples of modified MST prepared by Method 3 and the baseline MST exhibited very similar particle size distributions. (9) Dead-end filtration tests showed that the modified MST samples exhibited similar filtration characteristics as the baseline MST sample. (10) Performance testing indicated no change in strontium and neptunium removal after storing the modified MST for 6-months at ambient temperature. The results suggested that plutonium removal performance may be decreased slightly after 6-months of storage. However, the change in plutonium removal is not statistically significant at the 95% confidence limit. Based on these findings we recommend continued development of the modified MST as a replacement for the baseline MST for waste treatment facilities at the Savannah River Site.
Book Synopsis Tailoring Inorganic Sorbents for SRS Strontium and Actinide Separations by : DAVID. HOBBS
Download or read book Tailoring Inorganic Sorbents for SRS Strontium and Actinide Separations written by DAVID. HOBBS and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report summarizes experiments and engineering evaluations conducted in a project funded by the Department of Energy, Office of Environmental Cleanup and Acceleration to develop improved sorbent materials for strontium/actinide separations at SRS. From the results of Phase 1 activities of the project, we offer the following conclusions and recommendations. Chemically modified monosodium titanate (MST) samples exhibited significantly increased actinide removal performance compared to the baseline MST. Testing results indicate that the modified MST offers the possibility of reduced MST concentrations and shorter contact times compared to the baseline MST. Preliminary calculations indicate that the use of the optimized MST sorbent will provide significantly increased waste throughput in the ARP facilities should shorter batch contact times and reduced MST concentrations be realized. The maximum throughput increases are realized using a 0.1-micron pore-size filter media in these facilities. Evaluation of the impacts of incorporating MST into DWPF operations indicates that both the baseline MST and optimized MST (4X decrease) quantities can be accommodated from Chemical Processing Cell (CPC) and glass formulation perspectives. We recommend that the MST materials be tested to determine the effects, if any, that introduction of MST has on slurry rheology, antifoam effectiveness, potential generation of hydrogen and processing time in the CPC. Evaluation of the impacts of MST and titanosilicate analog of pharmacosiderite (TSP) materials determined that the use of these materials showed no significant impacts on the SWPF and Saltstone facility. Based on the promising enhanced actinide removal performance of the chemically modified MST samples, which could have significant positive impacts on the SWPF, ARP and perhaps an in-tank deployment for Sr/actinide removal, we recommend that the Department of Energy continue funding to develop chemically modified MST materials. Dried MST exhibited poorer strontium and alpha removal kinetics, which may adversely impact process cycle times and waste feed throughput. Thus, we recommend that pretreatment facilities not use dried MST. Samples of TSP, sodium nonatitanate (SNT) templated-MST and pH-adjusted MST materials did not exhibit significantly improved strontium and actinide removal performance compared to the baseline MST. Thus, we halted further development of these materials. Nb-SNT exhibited evidence of chemical instability upon contact with strongly alkaline salt solutions for several days. The chemical instability could have significant impacts on downstream operations in the SWPF and DWPF.
Book Synopsis TAILORING INORGANIC SORBENTS FOR SRS STRONTIUM AND ACTINIDE SEPARATIONS by :
Download or read book TAILORING INORGANIC SORBENTS FOR SRS STRONTIUM AND ACTINIDE SEPARATIONS written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This document provides a final report of Phase II testing activities for the development of a modified monosodium titanate (MST) that exhibits improved strontium and actinide removal characteristics compared to the baseline MST material. The activities included determining the key synthesis conditions for preparation of the modified MST, preparation of the modified MST at a larger scale by a commercial vendor, demonstration of the strontium and actinide removal characteristics with actual tank waste supernate and measurement of filtration characteristics. Key findings and conclusions include the following. Testing evaluated three synthetic methods and eleven process parameters for the optimum synthesis conditions for the preparation on an improved form of MST. We selected the post synthesis method (Method 3) for continued development based on overall sorbate removal performance. We successfully prepared three batches of the modified MST using Method 3 procedure at a 25-gram scale. The laboratory prepared modified MST exhibited increased sorption kinetics with simulated and actual waste solutions and similar filtration characteristics to the baseline MST. Characterization of the modified MST indicated that the post synthesis treatment did not significantly alter the particle size distribution, but did significantly increase the surface area and porosity compared to the original MST. Testing indicated that the modified MST exhibits reduced affinity for uranium compared to the baseline MST, reducing risk of fissile loading. Shelf-life testing indicated no change in strontium and actinide performance removal after storing the modified MST for 12-months at ambient laboratory temperature. The material releases oxygen during the synthesis and continues to offgas after the synthesis at a rapidly diminishing rate until below a measurable rate after 4 months. Optima Chemical Group LLC prepared a 15-kilogram batch of the modified MST using the post synthesis procedure (Method 3). Performance testing with simulated and actual waste solutions indicated that the material performs as well as or better than batches of modified MST prepared at the laboratory-scale. Particle size data of the vendor-prepared modified MST indicates a broader distribution centered at a larger particle size and microscopy shows more irregular particle morphology compared to the baseline MST and laboratory prepared modified MST. Stirred-cell (i.e., dead-end) filter testing revealed similar filtration rates relative to the baseline MST for both the laboratory and vendor-prepared modified MST materials. Crossflow filtration testing indicated that with MST-only slurries, the baseline MST produced between 30-100% higher flux than the vendor-prepared modified MST at lower solids loadings and comparable flux at higher solids loadings. With sludge-MST slurries, the modified MST produced 1.5-2.2 times higher flux than the baseline MST at all solids loadings. Based on these findings we conclude that the modified MST represents a much improved sorbent for the separation of strontium and actinides from alkaline waste solutions and recommend continued development of the material as a replacement for the baseline MST for waste treatment facilities at the Savannah River Site.
Book Synopsis Evaluation of New Inorganic Sorbents for Strontium and Actinide Removal from High-Level Nuclear Waste Solutions by :
Download or read book Evaluation of New Inorganic Sorbents for Strontium and Actinide Removal from High-Level Nuclear Waste Solutions written by and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Monosodium titanate (MST), a hydrous metal oxide sorbent, is the baseline material for the removal of 90Sr and alpha-emitting radionuclides (principally 238Pu, 239Pu, 240Pu and 237Np) from alkaline waste solutions generated during the processing of irradiated nuclear materials at the Savannah River Site. This material exhibits excellent performance characteristics for strontium removal. Plutonium removal is also good, but problematic at the estimated bonding concentration. We are currently developing new inorganic materials for improved sorption characteristics. These materials include sodium nonatitanates, pharmacosiderites and heteropolyniobates. We will present results evaluating the performance of these materials with simulated and actual high level nuclear waste solutions.
Book Synopsis Strontium and Actinide Sorption by MST and MMST Under Conditions Revelant to the Small Column Ion-Exchange Process by :
Download or read book Strontium and Actinide Sorption by MST and MMST Under Conditions Revelant to the Small Column Ion-Exchange Process written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of tests were performed to examine the kinetics of Sr and actinide removal by monosodium titanate (MST) and modified monosodium titanate (mMST) under mixing conditions similar to what will be provided in the Small Column Ion Exchange (SCIX) Program. Similar removal kinetics were seen for two different mixing energies, indicating that under these conditions bulk solution transport is not the rate limiting step for Sr and actinide removal. Sr removal was found to be rapid for both MST and mMST, reaching steady-state conditions within six hours. In contrast, at least six weeks is necessary to reach steady-state conditions for Pu with MST. For mMST, steady-state conditions for Pu were achieved within two weeks. The actual contact time required for the SCIX process will depend on starting sorbate concentrations as well as the requirements for the decontaminated salt solution. During testing leaks occurred in both the MST and mMST tests and evidence of potential desorption was observed. The desorption likely occurred as a result of the change in solids to liquid phase ratio that occurred due to the loss of solution. Based on these results, Savannah River National Laboratory (SRNL) recommended additional testing to further study the effect of changing phase ratios on desorption. This testing is currently in progress and results will be documented in a separate report.
Book Synopsis Strontium and Actinide Separations from High Level Nuclear Waste Solutions Using Monosodium Titanate - Actual Waste Testing by :
Download or read book Strontium and Actinide Separations from High Level Nuclear Waste Solutions Using Monosodium Titanate - Actual Waste Testing written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Pretreatment processes at the Savannah River Site will separate 9°Sr, alpha-emitting and radionuclides (i.e., actinides) and 137Cs prior to disposal of the high-level nuclear waste. Separation of 9°Sr and alpha-emitting radionuclides occurs by ion exchange/adsorption using an inorganic material, monosodium titanate (MST). Previously reported testing with simulants indicates that the MST exhibits high selectivity for strontium and actinides in high ionic strength and strongly alkaline salt solutions. This paper provides a summary of data acquired to measure the performance of MST to remove strontium and actinides from actual waste solutions. These tests evaluated the effects of ionic strength, mixing, elevated alpha activities, and multiple contacts of the waste with MST. Tests also provided confirmation that MST performs well at much larger laboratory scales (300-700 times larger) and exhibits little affinity for desorption of strontium and plutonium during washing.
Book Synopsis Screening Evaluation of Alternate Sorbents and Methods for Strontium and Actinide Removal from Alkaline Salt Solution by :
Download or read book Screening Evaluation of Alternate Sorbents and Methods for Strontium and Actinide Removal from Alkaline Salt Solution written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes results from screening tests evaluating strontium and actinide removal characteristics of three different titanium-containing sorbents, crystalline silicotitanate (CST) manufactured by UPO, SrTreat(R) offered by Fortum Engineering, sodium nonatitanate developed by Clearfield and coworkers at Texas A and M University and offered commercially by Honeywell. We also report results from an alternate removal method, coprecipitation.
Book Synopsis STRONTIUM AND ACTINIDE SEPARATIONS FROM HIGH LEVEL NUCLEAR WASTE SOLUTIONS USING MONOSODIUM TITANATE 1. SIMULANT TESTING. by : K. M. MARSHALL
Download or read book STRONTIUM AND ACTINIDE SEPARATIONS FROM HIGH LEVEL NUCLEAR WASTE SOLUTIONS USING MONOSODIUM TITANATE 1. SIMULANT TESTING. written by K. M. MARSHALL and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove {sup 137}Cs, {sup 90}Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal. Separation processes planned at SRS include caustic side solvent extraction, for {sup 137}Cs removal, and ion exchange/sorption of {sup 90}Sr and alpha-emitting radionuclides with an inorganic material, monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes {sup 238}Pu, {sup 239}Pu and {sup 240}Pu. This paper provides a summary of data acquired to measure the performance of MST to remove strontium and actinides from simulated waste solutions. These tests evaluated the influence of ionic strength, temperature, solution composition and the oxidation state of plutonium.
Book Synopsis Mechanisms of Strontium and Uranium Removal From Radioactive Waste Simulant Solutions by the Sorbent Monosodium Titanate by :
Download or read book Mechanisms of Strontium and Uranium Removal From Radioactive Waste Simulant Solutions by the Sorbent Monosodium Titanate written by and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: High-Level Radioactive Waste (HLW) is the priority problem for the U.S. Dept. of Energy's Environmental Management Program. Current HLW treatment processes at the Savannah River Site (Aiken, SC) include the use of monosodium titanate (MST, similar to NaTi2O5xH2O) to concentrate radioactive strontium (Sr) and actinides. Mechanistic information about radionuclide uptake will provide us with insight about the reliability of MST treatments. We characterized the morphology of MST and the chemistry of sorbed Sr{sup 2+} and uranium [U(VI)] on MST with x-ray based spectroscopic and electron microscopic techniques. Sorbed Sr{sup 2+} exhibited specific adsorption as partially-hydrated species, whereas sorbed U exhibited site-specific adsorption as monomeric and dimeric U(VI)-carbonate complexes. These differences in site specificity and mechanism may account for the difficulties associated with predicting MST loading and removal kinetics.
Book Synopsis Preparation and Use of Dried Monosodium Titanate by :
Download or read book Preparation and Use of Dried Monosodium Titanate written by and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report assesses the feasibility of handling MST in the SWPF and ARP facility as a dry solid versus that as an aqueous slurry. MST is an inorganic sorbent material that exhibits high selectivity for strontium and actinide elements in the presence of strongly alkaline and high sodium containing salt solutions. In addition to this assessment, the effects of drying on MST properties including strontium and actinide removal performance were also tested. This work represents two of the subtasks identified in the scope of work for the DOE funded project to develop improved sorbent materials for strontium/actinide separations at SRS.
Book Synopsis REVIEW OF EXPERIMENTAL STUDIES INVESTIGATING THE RATE OF STRONTIUM AND ACTINIDE ADSORPTION BY MONOSODIUM TITANATE. by :
Download or read book REVIEW OF EXPERIMENTAL STUDIES INVESTIGATING THE RATE OF STRONTIUM AND ACTINIDE ADSORPTION BY MONOSODIUM TITANATE. written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A number of laboratory studies have been conducted to determine the influence of mixing and mixing intensity, solution ionic strength, initial sorbate concentrations, temperature, and monosodium titanate (MST) concentration on the rates of sorbate removal by MST in high-level nuclear waste solutions. Of these parameters, initial sorbate concentrations, ionic strength, and MST concentration have the greater impact on sorbate removal rates. The lack of a significant influence of mixing and mixing intensity on sorbate removal rates indicates that bulk solution transport is not the rate controlling step in the removal of strontium and actinides over the range of conditions and laboratory-scales investigated. However, bulk solution transport may be a significant parameter upon use of MST in a 1.3 million-gallon waste tank such as that planned for the Small Column Ion Exchange (SCIX) program. Thus, Savannah River National Laboratory (SRNL) recommends completing the experiments in progress to determine if mixing intensity influences sorption rates under conditions appropriate for this program. Adsorption models have been developed from these experimental studies that allow prediction of strontium (Sr), plutonium (Pu), neptunium (Np) and uranium (U) concentrations as a function of contact time with MST. Fairly good agreement has been observed between the predicted and measured sorbate concentrations in the laboratory-scale experiments.
Book Synopsis Strontium and Actinides Removal from Savannah River Site Actual Waste Samples by Freshly Precipitated Manganese Oxide by : M. J. Barnes
Download or read book Strontium and Actinides Removal from Savannah River Site Actual Waste Samples by Freshly Precipitated Manganese Oxide written by M. J. Barnes 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 freshly precipitated manganese oxide and monosodium titanate (MST) for the removal of strontium (Sr) and actinides from actual high-level waste. Manganese oxide precipitation occurs upon addition of a reductant such as formate (HCO2- ) or peroxide (H2O2) to a waste solution containing permanganate (MnO4- ). Tests described in this document address the capability of manganese oxide treatment to remove Rs, Pu, and Np from actual high-level waste containing elevated concentrations of Pu. Additionally, tests investigate MST (using two unique batches) performance with the same waste for direct comparison to the manganese oxide performance.
Book Synopsis Demonstration of MST and Permanganate Efficiency on Removal of Actinides and Strontium from Savannah River Site High Level Waste by : T. B. Peters
Download or read book Demonstration of MST and Permanganate Efficiency on Removal of Actinides and Strontium from Savannah River Site High Level Waste written by T. B. Peters and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: We conducted a series of four demonstrations to determine the ability of either monosodium titanate (MST) or permanganate (MnO4- ) to remove strontium and actinides from salt solutions, under a variety of conditions. Each of the demonstrations used material derived from actual tank waste. The demonstrations used volumes as large as 68 L compared to typical prior experiments at 100 mL. Also, the study used, in two experiments, hydraulically scaled mixing conditions to match those of the equipment installed in Building 512-S for the Actinide Removal Process. (Plans call for radioactive commissioning of that facility as early as December 2003.).
Book Synopsis Phase I Technical Report for the Engineering of Monosodium Titanate by : CHARLES. NASH
Download or read book Phase I Technical Report for the Engineering of Monosodium Titanate written by CHARLES. NASH and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Monosodium titanate (MST) is an inorganic adsorbent that effectively removes strontium, plutonium, uranium, and other trace elements from alkaline salt supernate. Current plans use the MST in batch contact processes to treat Savannah River Site (SRS) waste solutions that require 90Sr and actinide removal to meet low level disposal criteria. More effective use of MST may be realized if the MST could be engineered into a form suitable for a continuous treatment process such as an adsorption column. The main benefits of column operation are (1) enhanced loading due to equilibration with feed adsorbate levels versus product levels, and (2) a small footprint relative to that of a batch contact tank. The current baseline MST material features particles of nominally 0.5-35 micron in size, which are much too fine for use in an adsorption column. An extensive review of the literature and consultation with technical experts identified candidate methods to produce engineered forms of MST. From this list a review team selected five candidate methods for further study. Laboratory syntheses at Savannah River National Laboratory (SRNL) and offsite produced representative samples for characterization and performance testing. Testing identified two suitable methods. The two methods include internal gelation, which is patented technology of Oak Ridge National Laboratory, and internal hydrolysis, a method in which the MST is produced within a porous substrate. A commercial sodium titanate, SrTreat(R), produced by Fortum Engineering (Finland), demonstrated good performance as well although plutonium removal kinetics appeared much slower than observed for the other engineered MST materials.
Book Synopsis Transmission Electron Microscopy Analysis of Strontium and Actinide-Bearing Monosodium Titanate and Permanganate Treatment Solids by : M. C. Duff
Download or read book Transmission Electron Microscopy Analysis of Strontium and Actinide-Bearing Monosodium Titanate and Permanganate Treatment Solids written by M. C. Duff and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The current design for the Salt Processing Facility at the SRS includes uses of monosodium titanate to remove and concentrate the strontium and actinides from high-level waste salt solutions.
