Download or read book Glass Formulation Development and Testing for the Vitrification of Cesium loaded Crystalline Silicotitanate CST written by and published by . This book was released on 1997 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Crystalline Silicotitanate (CST) is an inorganic ion exchange medium that was designed to sorb Cs-137, Sr-90 and several other radionuclides. CST exhibits high selectivity for the ion exchange of cesium from highly alkaline solutions containing large quantities of sodium. Through the Tanks Focus Area (TFA), Oak Ridge National Laboratory (ORNL) was funded to demonstrate the effectiveness of CST as an ion exchange material using supernate from the Melton Valley Storage Tanks (MVST). After processing the supernate through columns containing CST, the CST will be sluiced into drums and dewatered. Some of the CST will be shipped to the Savannah River Technology Center (SRTC) to demonstrate vitrification of the cesium-loaded CST in the shielded cells facility of SRTC. Vitrification is considered to be the Best Demonstrated Available Technology for immobilization of high-level waste and is currently being investigated for the treatment of low-level/mixed wastes. Vitrification of cesium-loaded CST offers a number of benefits. Vitrification: (1) is less expensive than many of the technologies available; (2) offers a large volume reduction; (3) produces a waste form that is very durable; (4) is an established technology; (5) can be used for a wide variety of waste streams; and (6) produces a waste form that is resistant to radiation damage. Prior to a full-scale demonstration, a glass formulation that will produce a glass that is both processable and durable must be developed. Crucible studies using unloaded CST and reagent grade glass-forming chemicals (or frit) were performed. Initially, scoping studies were performed to determine the chemicals necessary to form a glass. A screening experiment was then performed to determine the quantity of chemicals required. Finally, tests were conducted to determine the waste loading to be used during processing in the melter.
Download or read book Proceedings of the First International Conference on the Peaceful Uses of Atomic Energy written by and published by . This book was released on 1955 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Glass Formulation Development for the Vitrification of Oak Ridge Tank Waste written by and published by . This book was released on 1998 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: Crystalline silicotitanate (CST) is a highly specific ion exchange material for cesium. In particular, CST has been successfully demonstrated with both simulants and actual supernates from Savannah River and Hanford tank wastes. As a disposal option, vitrification of the cesium-loaded CST coupled with High-Level Waste (HLW) has been proposed. However, the CST sorbent contains significant quantities of titanium which historically have been difficult to incorporate into the glass structure. Therefore, nonradioactive tests using CST coupled with simulated HLW were performed to develop a glass formulation that would be both processable and durable. The results of the simulated crucible melts were verified using radioactive waste and cesium-loaded CST. This paper will detail the results of the formulation efforts.
Download or read book Papers on Illawarra Church Histories and the Mt Kembla Mine Disaster written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Compliance with the Nevada Test Site s Waste Acceptance Criteria for Vitrified Cesium loaded Crystalline Silicotitanate CST written by and published by . This book was released on 1997 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: Oak Ridge National Laboratory (ORNL) and Savannah River Technology Center (SRTC) are involved in a joint project for immobilization of radionuclides from the Melton Valley Storage Tanks (MVST) at Oak Ridge (OR). The supernate from Tank W-29 of the MVST will be treated by passage through a crystalline silicotitanate (CST) ion exchange medium. The CST was designed to sorb cesium, the primary radio nuclide (Cs-137) in the supernate of MVST's. A smaller amount of strontium (Sr-90) will also be sorbed. This demonstration will be performed by ORNL. One column volume of cesium-loaded CST ((approximately)10 gallons or 38 liters) will then be shipped to SRTC where it will be mixed with glass formers and fed as an aqueous slurry to a joule-heated melter within the SRTC Shielded Cells. A borosilicate glass formulation which will incorporate the CST has been developed as part oft SRTC's role in this project. The molten glass ((approximately)1150°C) will be poured into 500 ml stainless steel beakers which in turn will be placed in 30 gallon drums for disposal. An import & f part of this project is to demonstrate that the glass waste form produced will meet the Waste Acceptance Criteria (WAC) for disposal at the Nevada Test Site (NTS). If vitrification of the cesium-loaded CST is implemented as the immobilization method for all of the MVST supernate, then it is essential to demonstrate that the waste can be disposed of at an acceptable disposal facility. NTS accepts low-level radioactive waste as long as it is not TRU and not hazardous. This paper documents the efforts in the development stage of this work to integrate the requirements of NTS into the formulation and processing efforts. This work is funded by the Tank Focus Area with additional funding for ORNL provided by EM-30 at OR.
Download or read book Compliance with the Nevada Test Site s Waste Acceptance Criteria for Vitrified Cesium loaded Crystalline Silicotitanates written by and published by . This book was released on 1997 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of a joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC), Cs-137 loaded crystalline silicotitanate (CST) sorbent will be vitrified in a joule-heated melter. Glass formulation development for this CST sorbent is discussed in an accompanying abstract for this conference. One of the objectives for this project was to ensure that the vitrified waste form could be disposed of at the Nevada Test Site (NTS). To accomplish this objective, the waste form must meet the NTS Waste Acceptance Criteria (WAC). This paper presents SRTC's efforts at ensuring that the glass waste form produced as a result of vitrification of CST will meet all of the criteria of the WAC. The producer must demonstrate that the waste is neither TRU nor mixed, and that the glass has a radionuclide content which is less than the Class C limit of 4,600 Ci/m3. The impact of this requirement on the CST loading in the glass is discussed along with the benefits to the producer which result if greater than Class C waste is accepted by NTS since this limit may be relaxed in the near future. This paper demonstrates that vitrification leads to a waste form which meets all of the criteria of the NTS WAC.
Download or read book The Office of Environmental Management Technical Reports A Bibliography written by and published by DIANE Publishing. This book was released on 2001 with total page 245 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Office of Environmental Management's (EM) technical reports bibliography is an annual publication that contains information on scientific and technical reports sponsored by the Office of Environmental Management added to the Energy Science and Technology Database from July 1, 1994 through June 30, 1995. This information is divided into the following categories: Focus Areas, Cross-Cutting Programs, and Support Programs. In addition, a category for general information is included. EM's Office of Science and Technology sponsors this bibliography.
Download or read book EM written by and published by . This book was released on 1997 with total page 648 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Office of Environmental Management Technical Reports written by and published by . This book was released on 1997 with total page 972 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Office of Environmental Management Technical Reports written by and published by . This book was released on 1997 with total page 968 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IV written by James C. Marra and published by . This book was released on 1999 with total page 448 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Ceramic Abstracts written by and published by . This book was released on 1999 with total page 950 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1996 with total page 634 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Download or read book Ion Exchange written by C E Harland and published by Royal Society of Chemistry. This book was released on 2007-10-31 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt: Ion Exchange, 2nd Edition is a totally revised and updated version of the highly popular Monograph for Teachers, first published by The Royal Society of Chemistry in 1975. It covers the practical application of ion exchange and the synthesis of organic ion exchange resins, which have spanned nearly 60 years of development since the pioneering work of Adams and Holmes in 1935. This book covers the theory, development, and application in considerable detail and describes the history of development of ion exchange materials and the advances in their utilization in industrial processes. Key applications in such areas as water purification, hydrometallurgy, and chromatography are described and supported by chapters on the related scientific fundamentals governing equilibria and kinetics of ion exchange. Twenty-two experiments using inexpensive equipment are detailed, which not only complement a chapter dedicated to the characterization of organic exchangers, but also serve to illustrate several other pure and applied principles related to ion exchange phenomena. It is anticipated that the unique inclusion of experiments and the broad coverage of the whole text should appeal to a wide readership and offer particular relevance to practitioners in schools, colleges, and industry.
Download or read book State of the art Report on the Progress of Nuclear Fuel Cycle Chemistry written by and published by . This book was released on 2018 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt: The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel components is one of the advanced concepts being studied to help close the nuclear fuel cycle and to improve the long-term effects on the performance of geological repositories. Separating spent fuel elements and subsequently converting them through transmutation into short-lived nuclides should considerably reduce the longterm risks associated with nuclear power generation.
Download or read book Radioactive Waste Management and Contaminated Site Clean Up written by William E Lee and published by Elsevier. This book was released on 2013-10-31 with total page 925 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radioactive waste management and contaminated site clean-up reviews radioactive waste management processes, technologies, and international experiences. Part one explores the fundamentals of radioactive waste including sources, characterisation, and processing strategies. International safety standards, risk assessment of radioactive wastes and remediation of contaminated sites and irradiated nuclear fuel management are also reviewed. Part two highlights the current international situation across Africa, Asia, Europe, and North America. The experience in Japan, with a specific chapter on Fukushima, is also covered. Finally, part three explores the clean-up of sites contaminated by weapons programmes including the USA and former USSR. Radioactive waste management and contaminated site clean-up is a comprehensive resource for professionals, researchers, scientists and academics in radioactive waste management, governmental and other regulatory bodies and the nuclear power industry. Explores the fundamentals of radioactive waste including sources, characterisation, and processing strategies Reviews international safety standards, risk assessment of radioactive wastes and remediation of contaminated sites and irradiated nuclear fuel management Highlights the current international situation across Africa, Asia, Europe, and North America specifically including a chapter on the experience in Fukushima, Japan
