Download or read book Time Temperature Transformation Diagrams for DWPF Projected Glass Compositions written by and published by . This book was released on 1993 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Department of Energy's Waste Acceptance Product Specifications (WAPS) require that time-temperature-transformation diagrams be developed for each of the DWPF high-level waste glass compositions. This information will be useful in understanding the crystallization behavior during melter idling, accident scenarios, and storage. Simulated high level waste glass samples were annealed at temperatures varying from 400-1100°C for times varying from 45 minutes to 32 days. The glasses were characterized by x-ray diffraction to identify and quantify the crystalline phases present. The results were used to construct the diagrams.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 622 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book TIME TEMPERATURE TRANSFORMATION DIAGRAMS FOR THE SLUDGE BATCH 3 FRIT 418 GLASS SYSTEM written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: As a part of the Waste Acceptance Product Specifications (WAPS) for Vitrified High-Level Waste Forms defined by the Department of Energy - Office of Environmental Management, the phase stability must be determined for each of the projected high-level waste (HLW) types at the Savannah River Site (SRS). Specifically, WAPS 1.4.1 requires the glass transition temperature (Tg) to be defined and time-temperature-transformation (TTT) diagrams to be developed. The Tg of a glass is an indicator of the approximate temperature where the supercooled liquid converts to a solid on cooling or conversely, where the solid begins to behave as a viscoelastic solid on heating. A TTT diagram identifies the crystalline phases that can form as a function of time and temperature for a given waste type or more specifically, the borosilicate glass waste form. In order to assess durability, the Product Consistency Test (PCT) was used and the durability results compared to the Environmental Assessment (EA) glass. The measurement of glass transition temperature and the development of TTT diagrams have already been performed for the seven Defense Waste Processing Facility (DWPF) projected compositions as defined in the Waste Form Compliance Plan (WCP). These measurements were performed before DWPF start-up and the results were incorporated in Volume 7 of the Waste Form Qualification Report (WQR). Additional information exists for other projected compositions, but overall these compositions did not consider some of the processing scenarios now envisioned for DWPF to accelerate throughput. Changes in DWPF processing strategy have required this WAPS specification to be revisited to ensure that the resulting phases have been bounded. Frit 418 was primarily used to process HLW Sludge Batch 3 (SB3) at 38% waste loading (WL) through the DWPF. The Savannah River National Laboratory (SRNL) fabricated a cache of glass from reagent grade oxides to simulate the SB3-Frit 418 system at a 38 wt % WL for glass transition temperature measurement and TTT diagram development. The glass transition temperature (Tg) was measured using differential scanning calorimetry (DSC) and was recorded to be 443 ± 3 C. Using the previous TTT diagrams as guidance, subsamples of the glass were isothermally heat treated for 0.5 to 768 hours at temperatures between 400 C to 1100 C. Each of the 56 heat treated samples, along with quenched and centerline canister cooled (CCC) treated samples, were analyzed using Xray diffraction (XRD) and the PCT. Crystallization was detected only in samples treated at 600 C for more than 192 hours, and 700, 800, and 900 C for more than 48 hours. Phases crystallized were similar in composition if not the same as those found in the previous TTT studies. Six different crystalline phases were detected, including nepheline, acmite, lithium silicate, trevorite, krinovite, and albite. Overall, phases were spinel (iron) based, lithium metasilicate, sodium aluminosilicate or sodium transition metal silicate in composition. No new crystalline families were detected. Durability, as measured by the PCT, decreased when lithium silicate or nepheline crystals were present. Only one heat treated sample had a measured PCT response exceeding the benchmark EA glass, which was a sample treated at 600 C for 768 hours. During normal processing at the DWPF these conditions would be highly unlikely to occur, even in an extreme accident scenario. In order to continue to meet the requirements of the WCP, a simplified strategy is suggested for the generation of future TTT diagrams. A strategy has been developed that would require completing two more TTT diagrams for two averaged, future, predicted waste types. By creating diagrams for the resulting glass compositions of encompassing waste types, it will give insight to the crystallization regions possible for those averages. As discussed in the report, 'Initial MAR Assessments to Access the Impact of Al-Dissolution on DWPF Operating Windows' (WSRC-STI 2007-00688), the majority of waste compositions could be grouped into two future flowsheet scenarios, with and without Al-dissolution. Compositions Cluster 2 and Cluster 4 represent these waste projections. MAR assessments were completed on the two clusters and possible frits and windows of operation were selected for each projected waste type. It is recommended that a TTT diagram be developed for the following: (1) Cluster 2 combined with Frit-510 at a 34 wt % WL; and (2) Cluster 4 combined with Frit-418 at a 38 wt % WL. Given the results of the current study showed little change in the types of crystalline phases formed after heat treatment as compared to the TTT diagrams for the WCP glasses, it is unlikely that extreme differences will occur in the TTT diagram for future waste forms, as long as extreme waste stream changes or new frit components are not introduced.

Download or read book Radioactive Waste Management written by and published by . This book was released on 1981 with total page 726 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Durability of Simulated DWPF Annealed Glasses written by and published by . This book was released on 1993 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Simulated high-level waste glass samples of the DWPF projected compositions were annealed at various times and temperatures in order to develop time-temperature-transformation diagrams. These heat treated glasses were subjected to the Product Consistency Test (PCT) to evaluate glass durability. The B, Li, and Na concentrations in the leachate (the PCT results) were compared to the PCT results of the Environmental Assessment benchmark glass. Durability as a function of glass composition and crystallinity was also examined.

Download or read book Advances in Materials Science for Environmental and Nuclear Technology written by Kevin M. Fox and published by John Wiley & Sons. This book was released on 2010-10-01 with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Materials Science and Technology 2009 Conference and Exhibition (MS&T’09) was held October 25-29, 2009, in Pittsburgh, Pennsylvania. A major theme of the conference was Environmental and Energy Issues. Papers from three of the symposia held under that theme are included in this volume. These symposia include Materials Solutions for the Nuclear Renaissance; Green Engineering and Environmental Stewardship; and Nanotechnology for Energy. These symposia included a variety of presentations with sessions focused on sustainable energy, photovoltaics, nanowires and composites, energy harvesting, catalysts, thin films, corrosion, nuclear fuels, materials in aggressive environments, glass and ceramics for waste disposition, modeling and thermal properties, and education. Also included was a series of invited presentations and an international panel discussion on cement waste forms. The Green Engineering and Environmental Stewardship symposium was sponsored by the Nuclear and Environmental Technology Division (NETD) of The American Ceramic Society while the Materials Solutions for the Nuclear Renaissance symposium was sponsored by NETD and ASM International.

Download or read book TIME TEMPERATURE TRANSFORMATION TTT DIAGRAMS FOR FUTURE WASTE COMPOSITIONS written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: As a part of the Waste Acceptance Product Specifications (WAPS) for Vitrified High-Level Waste Forms defined by the Department of Energy - Office of Environmental Management, the waste form stability must be determined for each of the projected high-level waste (HLW) types at the Savannah River Site (SRS). Specifically, WAPS 1.4.1 requires the glass transition temperature (T{sub g}) to be defined and time-temperature-transformation (TTT) diagrams to be developed. The T{sub g} of a glass is an indicator of the approximate temperature where the supercooled liquid converts to a solid on cooling or conversely, where the solid begins to behave as a viscoelastic solid on heating. A TTT diagram identifies the crystalline phases that can form as a function of time and temperature for a given waste type or more specifically, the borosilicate glass waste form. In order to assess durability, the Product Consistency Test (PCT) was used and the durability results compared to the Environmental Assessment (EA) glass. The measurement of glass transition temperature and the development of TTT diagrams have already been performed for the seven Defense Waste Processing Facility (DWPF) projected compositions as defined in the Waste Form Compliance Plan (WCP) and in SRNL-STI-2009-00025. Additional phase transformation information exists for other projected compositions, but overall these compositions did not cover composition regions estimated for future waste processing. To develop TTT diagrams for future waste types, the Savannah River National Laboratory (SRNL) fabricated two caches of glass from reagent grade oxides to simulate glass compositions which would be likely processed with and without Al dissolution. These were used for glass transition temperature measurement and TTT diagram development. The glass transition temperatures of both glasses were measured using differential scanning calorimetry (DSC) and were recorded to be 448 C and 452 C. Using the previous TTT diagrams as guidance, subsamples of each glass were isothermally heat treated for 1 to 768 hours at temperatures between 500 C to 1000 C. Each of the heat treated samples, along with quenched and centerline canister cooled (CCC) treated samples, were analyzed using X-ray diffraction (XRD) and the PCT. Maximum crystallization was detected in samples treated at 700 C and 600 C for more than 96 hours in both glasses. Phases crystallized were similar in composition if not the same as those found in the previous TTT studies. Six different crystalline phases were detected, including nepheline, aegirine, lithium silicate, trevorite (spinel based), krinovite, and calcium magnesium iron silicon oxide. Overall, phases were spinel (iron) based, lithium metasilicate, sodium aluminosilicate or alkali transition metal silicate in composition. No new crystalline families were detected. Durability, as measured by the PCT, decreased when lithium silicate or nepheline crystals were present. The conclusions of this study were consistent with previous studies. In order to continue to meet the requirements of the WCP, a simplified strategy is suggested for the generation of future TTT diagrams. Only extremely significant changes in composition resulting from processing strategy changes would require generating more TTT diagrams.

Download or read book Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries VII written by Gary L. Smith and published by John Wiley & Sons. This book was released on 2012-03-28 with total page 389 pages. Available in PDF, EPUB and Kindle. Book excerpt: Composed from two symposia conducted at the 2001 Annual Meeting of The American Ceramic Society, this new volume details the advances in the state of knowledge in nuclear and waste materials science and technology. Highlighted are areas of rapid change such as in the application, development, and testing of ceramics and glasses in the nuclear and waste industries. As companies begin to focus on ¿green ceramics¿ and the manufacturing of environmentally friendly products, the development of innovative processing approaches and novel environmental treatment technologies soon follows. These are being developed to address more stringent regulations and to obtain an improved scientific understanding of the industrial processes and treatment technologies. This seventh volume in the series addresses current nuclear and environmental problems and provides solutions for them. It is an excellent resource for researchers and scientists involved in the ceramic and nuclear industries. roceedings of the symposium held at the 103rd Annual Meeting of The American Ceramic Society, April 22-25, 2001, in Indiana; Ceramic Transactions, Volume 132.

Download or read book Ceramic Abstracts written by and published by . This book was released on 1994 with total page 648 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 1993 with total page 988 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 written by and published by . This book was released on 2001 with total page 440 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.

Download or read book Government Reports Annual Index written by and published by . This book was released on 1993 with total page 1450 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Strategy and Methodology for Radioactive Waste Characterization written by International Atomic Energy Agency and published by IAEA. This book was released on 2007 with total page 188 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.

Download or read book Handbook of Advanced Radioactive Waste Conditioning Technologies written by Michael I. Ojovan and published by Elsevier. This book was released on 2011-01-24 with total page 505 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radioactive wastes are generated from a wide range of sources, including the power industry, and medical and scientific research institutions, presenting a range of challenges in dealing with a diverse set of radionuclides of varying concentrations. Conditioning technologies are essential for the encapsulation and immobilisation of these radioactive wastes, forming the initial engineered barrier required for their transportation, storage and disposal. The need to ensure the long term performance of radioactive waste forms is a key driver of the development of advanced conditioning technologies. The Handbook of advanced radioactive waste conditioning technologies provides a comprehensive and systematic reference on the various options available and under development for the treatment and immobilisation of radioactive wastes. The book opens with an introductory chapter on radioactive waste characterisation and selection of conditioning technologies. Part one reviews the main radioactive waste treatment processes and conditioning technologies, including volume reduction techniques such as compaction, incineration and plasma treatment, as well as encapsulation methods such as cementation, calcination and vitrification. This coverage is extended in part two, with in-depth reviews of the development of advanced materials for radioactive waste conditioning, including geopolymers, glass and ceramic matrices for nuclear waste immobilisation, and waste packages and containers for disposal. Finally, part three reviews the long-term performance assessment and knowledge management techniques applicable to both spent nuclear fuels and solid radioactive waste forms. With its distinguished international team of contributors, the Handbook of advanced radioactive waste conditioning technologies is a standard reference for all radioactive waste management professionals, radiochemists, academics and researchers involved in the development of the nuclear fuel cycle. Provides a comprehensive and systematic reference on the various options available and under development for the treatment and immobilisation of radioactive wastes Explores radioactive waste characterisation and selection of conditioning technologies including the development of advanced materials for radioactive waste conditioning Assesses the main radioactive waste treatment processes and conditioning technologies, including volume reduction techniques such as compaction

Download or read book Radioactive Waste Forms for the Future written by Werner Lutze and published by North Holland. This book was released on 1988 with total page 802 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume presents a compilation of important information on the full range of radioactive waste forms that have been developed, or at least suggested, for the incorporation of high-level nuclear waste. Many of the results were published in the ''gray literature'' of final reports of national laboratories or in various, generally less available, proceedings volumes. This is the first publication to draw information on nuclear waste forms for high-level wastes together into a single volume. Although borosilicate glass has become the standard waste form, additional research in this compound is still necessary. With improved technology (particularly processing technologies) and with a more detailed knowledge of repository conditions, glasses and second generation waste forms with improved performance properties can be developed. Sustained research programs on nuclear waste form development will yield results that can only add to public confidence and the final, safe disposal of nuclear waste. The aim of this volume is to provide a 'spring board' for these future research efforts. A detailed presentation is given on the properties and performance of non-crystalline waste forms (borosilicate glass, sintered glass, and lead-iron phosphate glass), and crystalline waste forms (Synroc, tailored ceramics, TiO 2 - ceramic matrix, glass-ceramics and FUETAP concrete). A chapter on Novel Waste Forms reviews a number of methods that warrant further development because of their potential superior performance and unique applications. The final chapter includes a tabulated comparison of important waste form properties and an extended discussion on the corrosion process and radiation damage effects for each waste form. Of particular interest is a performance assessment of nuclear waste borosilicate glass and the crystalline ceramic Synroc. This is the first detailed attempt to compare these two important waste forms on the basis of their materials properties. The discussion emphasizes the difficulties in making such a comparison and details the types of data that are required. Each chapter has been written by an expert and includes a current compilation of waste form properties with an extensive list of references. This volume will provide a stimulus for future research as well as useful reference material for scientists working in the field of nuclear waste disposal and materials science.

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 Data Analytics and Applications of the Wearable Sensors in Healthcare written by Shabbir Syed-Abdul and published by MDPI. This book was released on 2020-06-17 with total page 498 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book provides a collection of comprehensive research articles on data analytics and applications of wearable devices in healthcare. This Special Issue presents 28 research studies from 137 authors representing 37 institutions from 19 countries. To facilitate the understanding of the research articles, we have organized the book to show various aspects covered in this field, such as eHealth, technology-integrated research, prediction models, rehabilitation studies, prototype systems, community health studies, ergonomics design systems, technology acceptance model evaluation studies, telemonitoring systems, warning systems, application of sensors in sports studies, clinical systems, feasibility studies, geographical location based systems, tracking systems, observational studies, risk assessment studies, human activity recognition systems, impact measurement systems, and a systematic review. We would like to take this opportunity to invite high quality research articles for our next Special Issue entitled “Digital Health and Smart Sensors for Better Management of Cancer and Chronic Diseases” as a part of Sensors journal.