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Uranium And Plutonium Loading Onto Monosodium Titanate Mst In Tank 50h
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Book Synopsis URANIUM AND PLUTONIUM LOADING ONTO MONOSODIUM TITANATE MST IN TANK 50H. by : D. Hobbs
Download or read book URANIUM AND PLUTONIUM LOADING ONTO MONOSODIUM TITANATE MST IN TANK 50H. 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: A possible disposition pathway for the residue from the abandoned In-Tank Precipitation (ITP) sends the material from Tank 48H in increments to Saltstone via aggregation in Tank 50H. After entering Tank 50H, the amount of fissile material sorbed on MST may increase as a result of contacting waste solutions with dissolved uranium and plutonium. SRNL recommends that nuclear criticality safety evaluations use uranium and plutonium loadings onto MST of 14.0 {+-} 1.04 weight percent (wt %) for uranium and 2.79 {+-} 0.197 wt % for plutonium given the assumed streams defined in this report. These values derive from recently measured for conditions relevant to the Actinide Removal Process (ARP) and serve as conservative upper bounds for uranium and plutonium loadings during the proposed transfers of MST from Tank 48H into Tank 50H.
Book Synopsis Plutonium and Uranium Adsorption on Monosodium Titanate by :
Download or read book Plutonium and Uranium Adsorption on Monosodium Titanate written by and published by . This book was released on 1992 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Adsorption of Pu and U onto monosodium titanate (MST) in alkaline salt solution was measured. Changes in MST particle size distribution do not significantly affect the loadings of actinides. Max loading of plutonium-239 is 0.68 wt% at 0.79 mg/L Pu, below the infinitely safe value of 0.80 wt%. Max loading of uranium-235 onto MST is 1.4 wt% at a concentration of 20.3 ± 2.0 mg/L U, slightly higher than the calculated infinitely safe limit of 1.2 wt%. Experimental data indicated there is competition between plutonium and uranium for sites on the MST, and that the loading will favor the higher concentration species. Since the solubility of uranium is 10--100 times higher than of plutonium, uranium will be loaded to its maximum limit, but plutonium will be below its maximum limit. To ensure that the concentration of fissile materials cannot exceed nuclear safety limits, it is recommended that plutonium and uranium solubility tests be conducted with solutions which bound the compositions of waste which will be treated in ITP process.
Book Synopsis Fissile Solubility and Monosodium Titanate Loading Tests by :
Download or read book Fissile Solubility and Monosodium Titanate Loading Tests written by and published by . This book was released on 1993 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: The solubilities of plutonium and uranium have been determined for alkaline salt solutions having compositions which bound those which will be processed in the In-Tank Precipitation (ITP) process. Loadings of plutonium and uranium onto monosodium titanate (MST) have been determined at temperatures bounding those expected to occur during ITP and using a salt solution which was determined to have the maximum solubility for uranium and plutonium. Fissile loadings increase with decreasing amounts of MST in contact with the salt solutions saturated in plutonium and uranium. At MST concentrations bounding those which are planned for the ITP process, expressions for the maximum loadings (wt %) are determined to be 0.29 - 0.20x[MST] for plutonium and 1.8 - 0.29x[MST] for uranium, where [MST] is the concentration of MST in grams/liter. These expressions are valid over the range of MST concentrations from 0.05 to 0.51 g/L and temperatures of 17[degrees]--74[degrees]C. These loadings are below the individual infinitely safe limits for plutonium and uranium. Additional confirmatory experiments are planned to verify the effects of temperature and multiple contacts of the MST with fresh salt solution on the fissile loadings.
Book Synopsis Monosodium Titanate Particle Characterization by :
Download or read book Monosodium Titanate Particle Characterization written by and published by . This book was released on 1993 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: A characterization study was performed on monosodium titanate (MST) particles to determine the effect of high shear forces expected from the In-Tank Precipitation (ITP) process pumps on the particle size distribution. The particles were characterized using particle size analysis and scanning electron microscopy (SEM). No significant changes in particle size distributions were observed between as-received MST and after 2--4 hours of shearing. Both as-received and sheared MST particles contained a large percentage of porosity with pore sizes on the order of 500 to 2,000 Angstroms. Because of the large percentage of porosity, the overall surface area of the MST is dominated by the internal surfaces. The uranium and plutonium species present in the waste solution will have access to both interior and exterior surfaces. Therefore, uranium and plutonium loading should not be a strong function of MST particle size.
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 Prediction Models for Plutonium, Strontium, Uranium and Neptunium Loading Onto Monosodium Titanate (MST). by : T. B. Peters
Download or read book Prediction Models for Plutonium, Strontium, Uranium and Neptunium Loading Onto Monosodium Titanate (MST). written by T. B. Peters and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The DA isotherm parameters for U, Pu, Sr and Np have been updated to include additional data obtained since the original derivation. The DA isotherms were modified to include a kinetic function derived by Rahn to describe sorbate loading from the beginning of sorption up to equilibrium. The final functions describe both kinetic and thermodynamic sorption. We selected the Rahn function to describe radionuclide sorption because it originates from diffusion and absorption controlled sorption. An investigation of the thermal behavior of radionuclide sorption on MST as shown by this data revealed the sorption process is diffusion (or transport) controlled (in solution). Transport in solution can in theory be accelerated by vigorous mixing but the range of available mixing speed in the facility design will probably not be sufficient to markedly increase radionuclide sorption rate on MST from diffusion-controlled sorption. The laboratory studies included mixing energies hydraulically-scaled to match those of the Actinide Removal Process and these likely approximate the range of energies available in the Salt Waste Processing Facility.
Book Synopsis Determination of Fissile Loadings Onto Monosodium Titanate (MST) Under Conditions Relevant to the Actinide Removal Process Facility by : T. Peters
Download or read book Determination of Fissile Loadings Onto Monosodium Titanate (MST) Under Conditions Relevant to the Actinide Removal Process Facility written by T. Peters and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes the results of an experimental study to measure the sorption of fissile actinides on monosodium titanate (MST) at conditions relevant to operation of the Actinide Removal Process (ARP). The study examined the effect of a single contact of a large volume of radionuclide-spiked simulant solution with a small mass of MST. The volume of simulant to MST (8.5 L to 0.2 g of MST solids) was designed to mimic the maximum phase ratio that occurs between the multiple contacts of MST and waste solution and washing of the accumulated solids cycle of ARP. This work provides the following results. (1) After a contact time of {approx}2 weeks, we measured the following actinide loadings on the MST (average of solution and solids data), Pu: 2.79 {+-} 0.197 wt %, U: 14.0 {+-} 1.04 wt %, and Np: 0.839 {+-} 0.0178 wt %. (2) The plutonium and uranium loadings reported above are considerably higher than previously reported values. The higher loading result from the very high phase ratio and the high initial mass concentrations of uranium and plutonium. A separate upcoming document details the predicted values for this system versus the results. (3) The strontium DF values measured in these tests proved much lower than those reported previously with simulants having the same bulk chemical composition. The low strontium DF values reflect the very low initial mass concentration of strontium in this simulant (100 {micro}g/L) compared to that in previous testing ( 600 {micro}g/L).
Book Synopsis OPTIMIZED MONOSODIUM TITANATE PHASE II SUPPLEMENTAL TESTING REPORT URANIUM ADSORPTION AND SHELF-LIFE MEASUREMENTS. by :
Download or read book OPTIMIZED MONOSODIUM TITANATE PHASE II SUPPLEMENTAL TESTING REPORT URANIUM ADSORPTION AND SHELF-LIFE MEASUREMENTS. written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The DOE Office of Waste Processing recently funded supplemental Phase II testing to further investigate the uranium affinity and shelf-life of modified monosodium titanate (mMST). Testing results confirmed earlier findings that the mMST exhibits much lower affinity for uranium than the baseline monosodium titanate (MST) material. The loading of uranium onto the mMST sample measured more than an order of magnitude lower than that of the MST. This finding indicates that the use of mMST provides a significant advantage over MST in that the mMST will not concentrate enriched uranium to the degree that MST does. The reduced affinity of mMST for uranium allows more operational flexibility in treating waste solutions from a nuclear criticality safety perspective. Testing results also indicate that the mMST exhibits good shelf-life with no measurable loss in plutonium and neptunium removal upon storage of samples at ambient laboratory temperatures for up to 30-months. Testing did exhibit a change in strontium removal performance for both the mMST and MST samples at the most recent testing event. However, the decrease in strontium removal performance proved lower for the mMST than the MST sample. Given these positive findings SRNL recommends continued development of mMST as a replacement for MST in pretreatment facilities at the Savannah River Site (SRS).
Book Synopsis MONOSODIUM TITANATE MULTI-STRIKE TESTING. by :
Download or read book MONOSODIUM TITANATE MULTI-STRIKE TESTING. written by and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Research over the past decade has studied the adsorption of plutonium and uranium onto monosodium titanate (MST) in alkaline solutions. Tests showed that MST would remove the targeted radionuclides from simulated alkaline waste. Testing also indicated that Pu removal kinetics and Np capacity of the MST material impacts the size of equipment and waste blending plans for the Salt Waste Processing Facility (SWPF). Additionally, calculations suggested the baseline MST process may not achieve the desired decontamination in wastes containing elevated concentrations of Pu and Np. In this task, the authors investigated the performance of non-baseline process parameters and their effectiveness for treating waste feed in the Salt Waste Processing Facility. The work addresses a DOE request in support of technical needs expressed, in part, by the Engineering, Procurement, and Construction Contractors for the Salt Waste Processing Facility. The work investigated the effect of increased MST addition (up to 1.2 g/L) and the benefit of extra filtration steps with multiple additions of MST to salt waste containing actinides and strontium. Both simulant and actual waste testing occurred. Actual waste tests used a Tank 39H composite waste solution. In addition, testing to determine desorption of actinides from residual MST occurred. The release of sorbed Sr and actinides from loaded MST during the washing stages in the Salt Waste Processing Facility is an unresolved process behavior. Desorption tests assessed this potential problem using loaded MST from the residue of the MST adsorption tests. Analysis of non-radioactive Sr in the tests proved difficult due to the low concentration of nonradioactive Sr and its nearness to the method detection limit for ICP-MS. Efforts to use AMP to minimize dilution of actual waste for removal from the cell did not help for this analysis since instrument dilution still proved necessary due to the salt content.
Book Synopsis Engineering Monosodium Titanate for Adsorption Column Processes by : CHARLES. NASH
Download or read book Engineering Monosodium Titanate for Adsorption Column Processes 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 powder that effectively removes strontium, plutonium, neptunium, and other trace elements from alkaline high-level waste (HLW) supernate. This work tested one commercial titanate and four general methods to engineer MST into particles large enough to use in adsorption columns. The most successful of the engineered products selected from batch contact and chemical stability testing succeeded in treating 2900 bed volumes (BV) of simulated salt waste containing dissolved plutonium and strontium. There was no detectable strontium breakthrough and only 6 per cent plutonium breakthrough--well within the processing goal--at the end of the demonstration which operated at 5.3 BV/hour. Additional column tests at nominally 15 BV/hr demonstrated similar removal performance. Batch testing of adsorbents used both actual Savannah River Site (SRS) tank supernate as well as simulated salt solutions spiked with strontium, neptunium, and plutonium. In tank waste tests, internal gelation beads produced by the Oak Ridge National Laboratory (ORNL) demonstrated a batch distribution coefficient of 35,000 +/- 4,000 mL/g for plutonium at a phase ratio of 1970 mL/g. In the same batch the sorbent demonstrated a batch distribution coefficient of 99,000 +/- 7,500 mL/g for strontium. These results indicate that this material should be able to process thousands of bed volumes of SRS salt waste before column breakthrough.
Book Synopsis The 1996 Baseline Environmental Management Report: Report by :
Download or read book The 1996 Baseline Environmental Management Report: Report written by and published by . This book was released on 1996 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Capital Programming Guide by : United States. Office of Management and Budget
Download or read book Capital Programming Guide written by United States. Office of Management and Budget and published by . This book was released on 1997 with total page 116 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Ramjet Engines by : Mikhail Makarovich Bondari͡u︡k
Download or read book Ramjet Engines written by Mikhail Makarovich Bondari͡u︡k and published by . This book was released on 1969 with total page 466 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Pediatric Uroradiology by : R. Fotter
Download or read book Pediatric Uroradiology written by R. Fotter and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 770 pages. Available in PDF, EPUB and Kindle. Book excerpt: The text is specifically devoted to pediatric urogenital radiology. It covers all aspects of the subject in great depth, and contains essential information for the pediatrician, pediatric surgeon, and urologist. It is specifically designed to aid the clinician in decisions on imaging management. The technique and current value of all imaging and interventional procedures are presented, and the diverse problems associated with the changing anatomy, physiology, and pathophysiology of the growing organism are explained. Throughout, additional information is provided on operative options, postoperative complications, and clinical and radiological normal values. This book will prove of great interest to all who are involved in caring for children.
Download or read book Trichier written by Alessandra Ceretto and published by Lulu.com. This book was released on with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Yvain written by Chretien de Troyes and published by Yale University Press. This book was released on 1987-09-10 with total page 244 pages. Available in PDF, EPUB and Kindle. Book excerpt: A twelfth-century poem by the creator of the Arthurian romance describes the courageous exploits and triumphs of a brave lord who tries to win back his deserted wife's love
Book Synopsis Charles Pettigrew, First Bishop-elect of the North Carolina Episcopal Church by : Bennett H Wall
Download or read book Charles Pettigrew, First Bishop-elect of the North Carolina Episcopal Church written by Bennett H Wall and published by Hassell Street Press. This book was released on 2021-09-10 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work has been selected by scholars as being culturally important and is part of the knowledge base of civilization as we know it. This work is in the public domain in the United States of America, and possibly other nations. Within the United States, you may freely copy and distribute this work, as no entity (individual or corporate) has a copyright on the body of the work. Scholars believe, and we concur, that this work is important enough to be preserved, reproduced, and made generally available to the public. To ensure a quality reading experience, this work has been proofread and republished using a format that seamlessly blends the original graphical elements with text in an easy-to-read typeface. We appreciate your support of the preservation process, and thank you for being an important part of keeping this knowledge alive and relevant.
