Thermal and Chemical Stability of Baseline and Improved Crystalline Silicotitanate

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Total Pages : 5 pages
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Book Synopsis Thermal and Chemical Stability of Baseline and Improved Crystalline Silicotitanate by :

Download or read book Thermal and Chemical Stability of Baseline and Improved Crystalline Silicotitanate written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Savannah River Site (SRS) has been evaluating technologies for removing radioactive cesium (137Cs) from the supernate solutions stored in the high-level waste tanks at the site. Crystalline silicotitanate (CST) sorbent (IONSIV IE-911{reg_sign}, UOP LLC, Des Plaines, IL), which is very effective at removing cesium from high-salt solutions, was one of three technologies that were tested. Because of the extremely high inventory of 137Cs expected for the large columns of CST that would be used for treating the SRS supernate, any loss of flow or cooling to the columns could result in high temperatures from radiolytic heating. Also, even under normal operating conditions, the CST would be exposed to the supernates for up to a year before being removed. Small-scale batch and column tests conducted last year using samples of production batches of CST showed potential problems with CST clumping and loss of cesium capacity after extended contact with the simulant solutions. Similar tests-using samples of a baseline and improved granular CST and the CST powder used to make both granular samples-were performed this year to compare the performance of the improved CST. The column tests, which used recirculating supernate simulant, showed that the baseline CST generated more precipitates of sodium aluminosilicate than the improved CST. The precipitates were particularly evident in the tubing that carried the simulant solution to and from the column, but the baseline CST also showed higher concentrations of aluminum on the CST than were observed for the improved CST. Recirculating the simulant through just a section of the tubing (no contact with CST) also produced small amounts of precipitate, similar to the amounts seen for the improved CST column. The sodium aluminosilicate formed bridges between the CST granules, causing clumps of CST to form in the column. Clumps were visible in the baseline CST column after 1 month of operation and in the improved CST column after 2 months, For the baseline CST column, the clumps were routinely dispersed by backwashing the column with simulant. After 96 days of operation, a thin hard layer of CST formed on the bottom screen of the baseline column that restricted flow through the column. The bottom cap was removed and the CST was scraped from the screen to restore the column to normal operation. After 3 months of operation, the improved CST column was completely clumped together and could not be dispersed by backwashing. The pressure drop through the column was still relatively low, so the test was continued until the pressure drop increased to>15 psig after 105 days of operation. The column was then disassembled, and the CST was physically removed from the column and broken up. These results show that both the baseline and improved CST, when contacted with the supernate simulant, have the potential for forming clumps that can restrict the flow through the small columns used in these tests. The cesium capacity of the CST samples from the column tests with recirculating simulant decreased slightly as the run time increased. Most of this decrease could be attributed to the weight of cancrinite (a sodium aluminosilicate) on the CST samples. Tests conducted last year using production batch samples of CST showed a more pronounced drop in cesium capacity under comparable conditions. A column test using the improved CST and once-through simulant showed few problems during 5 months of operation. The pressure drop through the column remained low; however, when the final samples were taken after 5 months of operations, the CST in the column had clumped together. The final sample taken from the top 1 cm of the column showed a 65% drop in cesium capacity compared with all the other samples from this column. This sample also contained the highest concentration of cancrinite, but the weight of cancrinite could account for only a small fraction of the drop in cesium capacity by simple dilution of the CST. The CST in the batch tests stored at elevated temperatures in average simulant formed clumps, but this occurred at a slower rate than that observed last year during comparable tests using production batch samples of CST. Storage at elevated temperatures caused a gradual decrease in cesium capacity as the storage time increased, with a loss in capacity of up to 20% after 5 to 6 months at 80 C. The results for the baseline and improved CST samples were essentially the same for these batch tests.

Thermal and Chemical Stability of Crystalline Silicotitanate Sorbent

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ISBN 13 :
Total Pages : 36 pages
Book Rating : 4.:/5 (684 download)

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Book Synopsis Thermal and Chemical Stability of Crystalline Silicotitanate Sorbent by :

Download or read book Thermal and Chemical Stability of Crystalline Silicotitanate Sorbent written by and published by . This book was released on 2000 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Savannah River Site (SRS) is evaluating technologies for removing radioactive cesium (137Cs) from the supernate solutions stored in the high-level waste tanks at the site. Crystalline silicotitanate sorbent (IONSIV IE-911,{reg_sign} UOP LLC, Des Plaines, IL), which is very effective at removing cesium from high-salt solution, is one of three technologies currently being tested. Because of the extremely high inventory of 137Cs expected for the large columns of crystalline silicotitanate (CST) that would be used for treating the SRS supernate, any loss of flow or cooling to the columns could result in high temperatures from radiolytic heating. Also, even for normal operation, the CST would be exposed to the supernates for up to a year before being removed. Small-scale tests using simulant solutions were used to determine the long-term stability of the CST to the solutions at various temperatures. In the tests performed in this study, the cesium capacity of the CST decreased significantly (76%) as the temperature of the simulant and CST during loading was increased from 23 to 80 C. CST exposed to recirculating SRS average simulant solution at room temperature in a column test showed a slow decrease in cesium loading capacity (measured at 23 C), with a drop of 30% for CST from the top of the bed and 13% for CST from the bottom of the bed after a 12-month period of exposure. A similar column test using a high-pH salt solution did not show any change in the cesium capacity of the CST. An increase was noted in pressure drop through the column using average simulant, but no change was observed for the column using high-pH salt solution.

Objets d'art, porcelaines, faïences bronzes italiens et français

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ISBN 13 :
Total Pages : pages
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Download or read book Objets d'art, porcelaines, faïences bronzes italiens et français written by and published by . This book was released on 1912 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Scientific Basis for Nuclear Waste Management XXV

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ISBN 13 :
Total Pages : 960 pages
Book Rating : 4.:/5 (318 download)

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Book Synopsis Scientific Basis for Nuclear Waste Management XXV by : Materials Research Society. Meeting

Download or read book Scientific Basis for Nuclear Waste Management XXV written by Materials Research Society. Meeting and published by . This book was released on 2002 with total page 960 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume opens with a keynote lecture by Rodney Ewing, member of the Board of Radioactive Waste Management of the National Research Council. Ewing summarizes 25 years of materials research in nuclear waste, emphasizing the progress that has been made and the challenges that still confront investigators and technologists in materials science and repository performance evaluation. The session is followed by one on container materials and engineered barriers, and includes a discussion on the corrosion performance expected for waste packages in the proposed high-level nuclear waste repository at Yucca Mountain, Nevada. Invited papers on performance assessment and repository studies for different national programs are also highlighted, with representation from the United States, Sweden, Japan, Belgium, Switzerland, Italy, and the United Kingdom. A large number of papers focus on the structure, properties, and degradation of various waste forms such as glasses, ceramics (mostly for plutonium immobilization), cements, and spent nuclear fuel. For the second consecutive time, the number of papers on ceramics far exceeds those on glass, which had been the dominant material discussed at this symposium over the prior 23 years. New studies on zirconates confirm the recently discovered high radiation damage-resistance of this material. Additional topics include: performance assessment in high-level waste disposal; performance assessment in low-level waste disposal; ceramic structure and corrosion; radiation effects in ceramics; glass structure and corrosion; spent fuel; spent fuel cladding and alternative waste forms; cements in radioactive waste immobilization; contaminant transport; natural analogs; and waste processing.

Scientific Basis for Nuclear Waste Management XX: Volume 465

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ISBN 13 :
Total Pages : 1398 pages
Book Rating : 4.:/5 (318 download)

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Book Synopsis Scientific Basis for Nuclear Waste Management XX: Volume 465 by : Walter J. Gray

Download or read book Scientific Basis for Nuclear Waste Management XX: Volume 465 written by Walter J. Gray and published by . This book was released on 1997-07 with total page 1398 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book features scientific research that supports the safe and effective disposal of radioactive waste in a geological repository. One highlight of the volume is the opening talk by Rustum Roy, who was instrumental in establishing the first symposium on this topic in 1978. Professor Roy summarizes his views of the past 19 years of progress in the field. A second highlight is the participation by several Russian and Ukrainian scientists who authored papers on nuclear waste disposal aspects of the Chernobyl Unit 4 reactor that exploded in April 1986. Additional topics include: glass formulations and properties; glass/water interactions; cements in radioactive waste management; ceramic and crystalline waste forms; spent nuclear fuel; waste processing and treatment; radiation effects in ceramics, glasses and nuclear waste materials; waste package materials; radionuclide solubility and speciation; radionuclide sorption; radionuclide transport; repository backfill; performance assessment; natural analogues and excess plutonium dispositioning.

Scientific Basis for Nuclear Waste Management

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ISBN 13 :
Total Pages : 1368 pages
Book Rating : 4.X/5 (4 download)

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Book Synopsis Scientific Basis for Nuclear Waste Management by :

Download or read book Scientific Basis for Nuclear Waste Management written by and published by . This book was released on 1998 with total page 1368 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Scientific Basis for Nuclear Waste Management XXII: Volume 556

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ISBN 13 :
Total Pages : 1370 pages
Book Rating : 4.:/5 (318 download)

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Book Synopsis Scientific Basis for Nuclear Waste Management XXII: Volume 556 by : David J. Wronkiewicz

Download or read book Scientific Basis for Nuclear Waste Management XXII: Volume 556 written by David J. Wronkiewicz and published by . This book was released on 1999-11-24 with total page 1370 pages. Available in PDF, EPUB and Kindle. Book excerpt: Safe and effective management of nuclear waste provides a broad range of challenges for materials science. Waste processing, waste form and engineered barrier properties, interactions between engineered and geological systems, radiation effects, chemistry and transport of waste species, and long-term predictions of repository performance are just some of the scientific problems facing modern society. This book, the 22nd in a very successful series from MRS, offers an international and inter-disciplinary perspective on the issues, and features developments in both fundamental and applied areas. Topics include: development and characterization of ceramic waste forms; ceramic waste form corrosion; glass waste form processing; glass formulation, properties and structure; glass waste form corrosion; spent nuclear fuel; performance assessment; repository backfill; flow and transport; natural analogues; container corrosion; metal waste form corrosion; radionuclide speciation and solubility; radionuclide sorption; microbial effects; radiation effects; cement waste forms and waste treatment.

Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site

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Publisher : National Academies Press
ISBN 13 : 0309075939
Total Pages : 96 pages
Book Rating : 4.3/5 (9 download)

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Book Synopsis Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site by : National Research Council

Download or read book Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site written by National Research Council and published by National Academies Press. This book was released on 2001-09-03 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. Department of Energy (DOE) is nearing a decision on how to process 30 million gallons of high-level radioactive waste salt solutions at the Savannah River Site in South Carolina to remove strontium, actinides, and cesium for immobilization in glass and eventual shipment to a geologic repository. The department is sponsoring research and development (R&D) work on four alternative processes and plans to use the results to make a downselection decision in a June 2001 time frame. The DOE requested that the National Research Council help inform this decision by addressing the following charge: evaluate the adequacy of the criteria that will be used by the department to select from among the candidate processes under consideration; evaluate the progress and results of the research and development work that is being undertaken on these candidate processes; and assess whether the technical uncertainties have been sufficiently resolved to proceed with downsizing the list of candidate processes. Responses to the last two points are provided in this report. Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site focuses exclusively on the technical issues related to the candidate processes for radionuclide removal from high-level waste salt solutions at SRS. The committee's interim report served as a response to the first point of this charge, and may be read in Appendix B. In that report, the committee found that DOE's proposed criteria are an acceptable basis for selecting among the candidate processes under consideration, but that the criteria should not be implemented in a way that relies on a single numerical "total score."

Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries

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ISBN 13 :
Total Pages : 720 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries by :

Download or read book Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries written by and published by . This book was released on 2000 with total page 720 pages. Available in PDF, EPUB and Kindle. Book excerpt: Consists of proceedings of various symposia held during the Annual Meeting of the American Ceramic Society.

Inorganic Ion Exchange Materials

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Publisher : CRC Press
ISBN 13 : 1351090461
Total Pages : 391 pages
Book Rating : 4.3/5 (51 download)

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Book Synopsis Inorganic Ion Exchange Materials by : Clearfield

Download or read book Inorganic Ion Exchange Materials written by Clearfield and published by CRC Press. This book was released on 2018-02-01 with total page 391 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book extends the frontiers of the ion exchange technologist and highlights new materials for the future.

Cementitious Materials for Nuclear Waste Immobilization

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Publisher : John Wiley & Sons
ISBN 13 : 1118512006
Total Pages : 245 pages
Book Rating : 4.1/5 (185 download)

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Book Synopsis Cementitious Materials for Nuclear Waste Immobilization by : Rehab O. Abdel Rahman

Download or read book Cementitious Materials for Nuclear Waste Immobilization written by Rehab O. Abdel Rahman and published by John Wiley & Sons. This book was released on 2014-11-17 with total page 245 pages. Available in PDF, EPUB and Kindle. Book excerpt: Cementitious materials are an essential part in any radioactive waste disposal facility. Conditioning processes such as cementation are used to convert waste into a stable solid form that is insoluble and will prevent dispersion to the surrounding environment. It is incredibly important to understand the long-term behavior of these materials. This book summarises approaches and current practices in use of cementitious materials for nuclear waste immobilisation. It gives a unique description of the most important aspects of cements as nuclear waste forms: starting with a description of wastes, analyzing the cementitious systems used for immobilization and describing the technologies used, and ending with analysis of cementitious waste forms and their long term behavior in an envisaged disposal environment. Extensive research has been devoted to study the feasibility of using cement or cement based materials in immobilizing and solidifying different radioactive wastes. However, these research results are scattered. This work provides the reader with both the science and technology of the immobilization process, and the cementitious materials used to immobilize nuclear waste. It summarizes current knowledge in the field, and highlights important areas that need more investigation. The chapters include: Introduction, Portland cement, Alternative cements, Cement characterization and testing, Radioactive waste cementation, Waste cementation technology, Cementitious wasteform durability and performance assessment.

Annual Meeting Abstracts

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ISBN 13 :
Total Pages : 442 pages
Book Rating : 4.0/5 ( download)

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Book Synopsis Annual Meeting Abstracts by : American Ceramic Society. Meeting

Download or read book Annual Meeting Abstracts written by American Ceramic Society. Meeting and published by . This book was released on 1999 with total page 442 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Radiation and Thermal Effects of Zeolites, Smectites and Crystalline Silicotitanates

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ISBN 13 :
Total Pages : 472 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Radiation and Thermal Effects of Zeolites, Smectites and Crystalline Silicotitanates by : Binxi Gu

Download or read book Radiation and Thermal Effects of Zeolites, Smectites and Crystalline Silicotitanates written by Binxi Gu and published by . This book was released on 2001 with total page 472 pages. Available in PDF, EPUB and Kindle. Book excerpt:

An Introduction to Nuclear Waste Immobilisation

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Publisher : Elsevier
ISBN 13 : 0080455719
Total Pages : 334 pages
Book Rating : 4.0/5 (84 download)

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Book Synopsis An Introduction to Nuclear Waste Immobilisation by : Michael I. Ojovan

Download or read book An Introduction to Nuclear Waste Immobilisation written by Michael I. Ojovan and published by Elsevier. This book was released on 2010-07-07 with total page 334 pages. Available in PDF, EPUB and Kindle. Book excerpt: Safety and environmental impact is of uppermost concern when dealing with the movement and storage of nuclear waste. The 20 chapters in 'An Introduction to Nuclear Waste Immobilisation' cover all important aspects of immobilisation, from nuclear decay, to regulations, to new technologies and methods. Significant focus is given to the analysis of the various matrices used in transport: cement, bitumen and glass, with the greatest attention being given to glass. The last chapter concentrates on the performance assessment of each matrix, and on new developments of ceramics and glass composite materials, thermochemical methods and in-situ metal matrix immobilisation. The book thoroughly covers all issues surrounding nuclear waste: from where to locate nuclear waste in the environment, through nuclear waste generation and sources, treatment schemes and technologies, immobilisation technologies and waste forms, disposal and long term behaviour. Particular attention is paid to internationally approved and worldwide-applied approaches and technologies.* Each chapter focuses on a different matrix used in nuclear waste immobilisation: Cement, bitumen, glass and new materials.* Keeps the most important issues surrounding nuclear waste – such as treatment schemes and technologies, and disposal - at the forefront.

Science and Technology for Disposal of Radioactive Tank Wastes

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Publisher : Springer Science & Business Media
ISBN 13 : 1489915435
Total Pages : 513 pages
Book Rating : 4.4/5 (899 download)

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Book Synopsis Science and Technology for Disposal of Radioactive Tank Wastes by : Wallace W. Shulz

Download or read book Science and Technology for Disposal of Radioactive Tank Wastes written by Wallace W. Shulz and published by Springer Science & Business Media. This book was released on 2013-11-11 with total page 513 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radioactive wastes resulting from over 40 years of production of nuclear weapons in the U. S. are currently stored in 273 underground tanks at the U. S. Department of Energy Hanford site, Idaho National Engineering and Environmental Laboratory, Oak Ridge Reservation, and Savannah River site. Combined, tanks at these sjtes contain approximately 94,000,000 gallons of waste in a variety of forms including liquid, concrete-like salt cake, and various sludges. More than 730,000,000 curies of several radioactive isotopes are present in the underground tanks. Certainly, one of the greatest challenges facing the U. S. Department of Energy is how to characterize, retrieve, treat, and immobilize the great variety of tank wastes in a safe, timely, and cost-effective manner. For several years now, the U. S. Department of Energy has initiated and sponsored scientific and engineering studies, tests, and demonstrations to develop the myriad of technologies required to dispose of the radioactive tank wastes. In recent times, much of the Department of Energy R&D activities concerning tank wastes have been closely coordinated and organized through the Tanks Focus Area (IF A); responsibility for technical operations of the TF A has been assigned to the Pacific Northwest National Laboratory.

Energy Materials Coordinating Committe (EMaCC): Fiscal Year 1999 Annual Technical Report

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Publisher : DIANE Publishing
ISBN 13 : 1422345645
Total Pages : 221 pages
Book Rating : 4.4/5 (223 download)

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Book Synopsis Energy Materials Coordinating Committe (EMaCC): Fiscal Year 1999 Annual Technical Report by :

Download or read book Energy Materials Coordinating Committe (EMaCC): Fiscal Year 1999 Annual Technical Report written by and published by DIANE Publishing. This book was released on with total page 221 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Chemical Abstracts

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ISBN 13 :
Total Pages : 2668 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Chemical Abstracts by :

Download or read book Chemical Abstracts written by and published by . This book was released on 2002 with total page 2668 pages. Available in PDF, EPUB and Kindle. Book excerpt: