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Mechanisms Of Strontium And Uranium Removal From Radioactive Waste Simulant Solutions By The Sorbent Monosodium Titanate
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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 Mechanisms of Strontium and Uranium Removal from High-Level Radioactive Waste Simulant Solutions by the Sorbent Monosodium Titanate by :
Download or read book Mechanisms of Strontium and Uranium Removal from High-Level Radioactive Waste Simulant Solutions by the Sorbent Monosodium Titanate written by and published by . This book was released on 2003 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-Level Waste (HLW) is a waste associated with the dissolution of spent nuclear fuel for the recovery of weapons-grade material. It is the priority problem for the U.S. Department of Energy's Environmental Management Program. Current HLW treatment processes at the Savannah River Site (Aiken, SC) include the use of monosodium titanate. The local structural speciation of sorbed U varied with loading but not for Sr. Sorbed Sr exhibited specific adsorption as partially-hydrated species whereas sorbed U exhibited specific adsorption as monomeric and dimeric U(VI)-carbonate complexes. Sorption proved site specific. These differences in site specificity and sorption mechanism may account for the difficulties associated with predicting Sr and U loading and removal kinetics using MST.
Author :Brookhaven National Laboratory. National Synchrotron Light Source Publisher : ISBN 13 : Total Pages :226 pages Book Rating :4.:/5 (89 download)
Book Synopsis Activity report by : Brookhaven National Laboratory. National Synchrotron Light Source
Download or read book Activity report written by Brookhaven National Laboratory. National Synchrotron Light Source and published by . This book was released on 2004 with total page 226 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 Metal Resistance in Microorganisms by : Rob Van Houdt
Download or read book Metal Resistance in Microorganisms written by Rob Van Houdt and published by Frontiers Media SA. This book was released on 2022-05-03 with total page 168 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Phase IV Testing of Monosodium Titanate Adsorption with Radioactive Waste by :
Download or read book Phase IV Testing of Monosodium Titanate Adsorption with Radioactive Waste written by and published by . This book was released on 1999 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Testing examined the extent and rate of strontium, plutonium, uranium, and neptunium removal from radioactive waste solutions at 4.5M and 7.5M in Na concentration by adsorption onto monosodium titanate (MST) at 0.2 g/L. Results indicate that the extents and rates of strontium, plutonium, and neptunium removal in radioactive waste solutions agree well with those previously measured using simulated waste solutions. Uranium removal in the 7.5M Na radioactive waste solution proved similar to that observed with simulated waste solutions. Uranium removal in the 4.5M Na radioactive waste solution proved lower than expected from previous simulant tests. The authors conclude that MST adsorption data obtained from simulated waste solutions provide reliable predictions for use in facility design and flowsheet modeling studies in the Salt Disposition Alternatives program.
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 Zweite Gegenantwort auf die Antwort des Herrn Philibert Obernetters betreffend die Zugab zu dem Etwas by :
Download or read book Zweite Gegenantwort auf die Antwort des Herrn Philibert Obernetters betreffend die Zugab zu dem Etwas written by and published by . This book was released on 1783 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Selective Removal of Strontium and Cesium from Simulated Waste Solution with Titanate Ion-Exchangers in a Filter Cartridge CONFIGURATIONS-12092 by :
Download or read book Selective Removal of Strontium and Cesium from Simulated Waste Solution with Titanate Ion-Exchangers in a Filter Cartridge CONFIGURATIONS-12092 written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Experimental results for the selective removal of strontium and cesium from simulated waste solutions with monosodium titanate and crystalline silicotitanate laden filter cartridges are presented. In these proof-of-principle tests, effective uptake of both strontium-85 and cesium-137 were observed using ion-exchangers in this filter cartridge configuration. At low salt simulant conditions, the instantaneous decontamination factor for strontium-85 with monosodium titanate impregnated filter membrane cartridges measured 26, representing 96% strontium-85 removal efficiency. On the other hand, the strontium-85 instantaneous decontamination factor with co-sintered active monosodium titanate cartridges measured 40 or 98% Sr-85 removal efficiency. Strontium-85 removal with the monosodium titanate impregnated membrane cartridges and crystalline silicotitanate impregnated membrane cartridges, placed in series arrangement, produced an instantaneous decontamination factor of 41 compared to an instantaneous decontamination factor of 368 for strontium-85 with co-sintered active monosodium titanate cartridges and co-sintered active crystalline silicotitanate cartridges placed in series. Overall, polyethylene co-sintered active titanates cartridges performed as well as titanate impregnated filter membrane cartridges in the uptake of strontium. At low ionic strength conditions, there was a significant uptake of cesium-137 with co-sintered crystalline silicotitanate cartridges. Tests results with crystalline silicotitanate impregnated membrane cartridges for cesium-137 decontamination are currently being re-evaluated. Based on these preliminary findings we conclude that incorporating monosodium titanate and crystalline silicotitanate sorbents into membranes represent a promising method for the semicontinuous removal of radioisotopes of strontium and cesium from nuclear waste solutions.
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 Characterization of Strontium and Manganese Oxide Solids Formed from Permanganate Reduction During Simulant Radioactive Waste Treatment by : M. C. Duff
Download or read book Characterization of Strontium and Manganese Oxide Solids Formed from Permanganate Reduction During Simulant Radioactive Waste Treatment 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: Nearly 34 million gallons of high-level waste (HLW, the radioactive waste product associated with the dissolution of spent nuclear fuel rods for the recovery of weapons grade materials) await disposition at the Savannah River Site (SRS). The current design for the Salt Waste Processing Facility at the SRS includes use of monosodium titanate (MST) to remove and concentrate the strontium (Sr) and actinides (uranium, plutonium and neptunium) from HLW salt solutions. However, the River Protection Program (RPP) at the Hanford Site in Washington State proposes use of potassium permanganate addition for Sr and actinide removal from Hanford HLW. Recent studies at the SRS indicate sodium permanganate treatment holds promise for use in the decontamination of Sr and actinides in SRS HLW.
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 Removal of Radioactive Strontium, Iodine, and Uranium from Contaminated Groundwater by : Mary E. Leonard
Download or read book Removal of Radioactive Strontium, Iodine, and Uranium from Contaminated Groundwater written by Mary E. Leonard and published by . This book was released on 2017 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt: Iodine-129 is a key risk driver at sites where nuclear materials have been fabricated or processed, and it is a predominant isotope of concern in long-term waste storage strategies. I-129 exists primarily as iodate in the subsurface at the Hanford Site in south-central Washington State. Between 15 and 40% of I-129 in the Hanford vadose zone is present in organoiodine form, with the remainder being iodide. Very few alternatives are available for immobilization of dissolved I-129, and the complex biogeochemical behavior of iodine in multiple forms makes it particularly challenging in the context of immobilization. In this work, two Bi-based layered materials for the sequestration of radioactive iodate and iodide were synthesized and characterized. Each material showed remarkable selectivity for iodate, with a maximum K[subscript d] of 2810 mL/g observed in groundwater containing high concentrations of carbonate and other competing anions. One of the sorbents displayed nearly quantitative uptake of total iodine, including organoiodine, from Hanford groundwater. Iodide removal was dominated by ion exchange, while iodate immobilization appears to have occurred through a combination of redox and ion-exchange processes. Each sorbent outperformed previously reported non-redox active hydrotalcites in removing iodate from groundwater. Together, these materials comprise a significant step forward for subsurface iodine removal strategies. Another radioactive contaminant of concern present in the Hanford subsurface is strontium-90. Sr-90 is a fission product of uranium, and it has entered the environment as a consequence of nuclear weapons testing, fuel reprocessing activity, and accidental or intentional releases. When ingested, strontium is deposited in bone tissue and teeth. Exposure to Sr-90 increases the risk of leukemia, bone sarcoma, and a number of other health problems. Removing it from contaminated groundwater and preventing its migration in subsurface sediments is of major importance to ongoing remediation efforts at the Hanford Site. Three inorganic sorbent materials--IONSIV IE-911, IONSIV IE-96, and bone charcoal--were studied in this work. Each sorbent effectively removed strontium from groundwater simulant (GWS) formulated to match groundwater collected at the Hanford Site. Sorption isotherms and kinetics were established for each sorbent in this system, and their maximum sorption capacities for strontium in GWS determined. A third major contaminant at the Hanford Site is uranium, which has entered the vadose zone through multiple routes, including leaks from high-level waste storage tanks and percolation into soil from unlined cribs and retention trenches. Removal of uranium from groundwater simulant by IONSIV IE-911, IONSIV IE-96, and bone charcoal was evaluated. The impact of uranium on strontium uptake by the sorbents in GWS was quantified, and the influence of uranium on speciation of strontium and calcium was examined. In order to discern actual sorption from precipitation of uranium, the fate of uranium in the contact solutions and sorbents was determined spectrophotometrically. Aqueous speciation of uranium in the GWS was modelled in simulations performed with two geochemical modelling software packages, MINTEQ and PHREEQC. Results of the simulations were compared to experimental data. The formation of aqueous ternary alkaline earth carbonate species of uranium (VI) and mechanisms of uranium sorption via surface complexation were considered.
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 Phase V Simulant Testing of Monosodium Titanate Adsorption Kinetics by :
Download or read book Phase V Simulant Testing of Monosodium Titanate Adsorption Kinetics written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Testing examined the extent and rate of strontium, plutonium, neptunium, and uranium removal from a 5.6 M Na solution by adsorption onto monosodium titanate (MST) at 0.2 and 0.4 g/L. Previously, Phase IV tests determined removal characteristics with solutions at 4.5M and 7.5M Na concentrations. These latest tests evaluated removal at the Na concentration expected for the Non-elutable Ion Exchange (N-IX) and Caustic Side Solvent Extraction (CSSE) flowsheets. Results indicated decreased sorbate removal from a 5.6M Na solution compared to a 4.5M Na solution. Strontium and plutonium removal produced equilibrium concentrations below Z-area feed limits under certain conditions, which indicated that the isotopic distribution of strontium and plutonium must be considered in design for feed blending strategies. Neptunium removal did not achieve the Z-Area limit at either MST concentration although the addition of 0.4 g/L MST nearly achieved the limit. The results indicated that strontium and plutonium removal rates decrease with increased sodium concentration (i.e., ionic strength). Neptunium and uranium removal proved lower from the 5.6M Na solution than the 7.5M Na solutions. These results provide additional data for sizing continuously stirred tank reactors for the Small Tank Tetraphenylborate (STTB) process and processing tanks for a strontium and alpha removal unit operation in the CSSE and N-IX processes.
Book Synopsis Development of an Improved Titanate-Based Sorbent for Strontium and Actinide Separations Under Strongly Alkaline Conditions by :
Download or read book Development of an Improved Titanate-Based Sorbent for Strontium and Actinide Separations Under Strongly Alkaline Conditions written by and published by . This book was released on 2010 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 134,137}Cs, 9°Sr, and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes at SRS include the sorption of 9°Sr and alpha-emitting radionuclides onto monosodium titanate (MST) and caustic side solvent extraction of 137Cs. The MST and separated 137Cs is encapsulated along with the sludge fraction of high-level waste (HLW) into a borosilicate glass waste form for eventual entombment at a federal repository. The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes 238Pu, 239Pu, and 24°Pu; 237Np; and uranium isotopes, 235U and 238U. This paper describes recent results evaluating the performance of an improved sodium titanate material that exhibits increased removal kinetics and capacity for 9°Sr and alpha-emitting radionuclides compared to the current baseline material, MST.
Book Synopsis CHARACTERIZATION OF MODIFIED MONOSODIUM TITANATE - AN IMPROVED SORBENT FOR STRONTIUM AND ACTINIDE SEPARATIONS. by :
Download or read book CHARACTERIZATION OF MODIFIED MONOSODIUM TITANATE - AN IMPROVED SORBENT FOR 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: High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove {sup 134,137}Cs, 9°Sr, and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. An inorganic sorbent, monosodium titanate (MST), is currently used to remove 9°Sr and alpha-emitting radionuclides, while a caustic-side solvent extraction process is used for removing {sup 134,137}Cs. A new peroxotitanate material, modified MST, or mMST, has recently been developed and has shown increased removal kinetics and capacity for 9°Sr and alpha-emitting radionuclides compared to the current baseline material, MST. This paper describes recent results focused on further characterization of this material.
