High-level Nuclear Waste Borosilicate Glass
High-level Nuclear Waste Borosilicate Glass

Author:

Publisher:

Published: 1992

Total Pages: 9

ISBN-13:

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With the imminent startup, in the United States, of facilities for vitrification of high-level nuclear waste, a document has been prepared that compiles the scientific basis for understanding the alteration of the waste glass products under the range of service conditions to which they may be exposed during storage, transportation, and eventual geologic disposal. A summary of selected parts of the content of this document is provided. Waste glass alterations in a geologic repository may include corrosion of the glass network due to groundwater and/or water vapor contact. Experimental testing results are described and interpreted in terms of the underlying chemical reactions and physical processes involved. The status of mechanistic modeling, which can be used for long-term predictions, is described and the remaining uncertainties associated with long-term simulations are summarized.

Handbook of Advanced Radioactive Waste Conditioning Technologies
Handbook of Advanced Radioactive Waste Conditioning Technologies

Author: Michael I. Ojovan

Publisher: Elsevier

Published: 2011-01-24

Total Pages: 505

ISBN-13: 085709095X

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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

Radioactive Waste Forms for the Future
Radioactive Waste Forms for the Future

Author: Werner Lutze

Publisher: North Holland

Published: 1988

Total Pages: 802

ISBN-13:

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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.

Cementitious Materials for Nuclear Waste Immobilization
Cementitious Materials for Nuclear Waste Immobilization

Author: Rehab O. Abdel Rahman

Publisher: John Wiley & Sons

Published: 2014-11-17

Total Pages: 245

ISBN-13: 1118512006

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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.

Radioactive Waste Forms for the Future
Radioactive Waste Forms for the Future

Author: Werner Lutze

Publisher: North Holland

Published: 1988

Total Pages: 800

ISBN-13:

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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.

Leaching of Fully Radioactive High-level Waste Glass
Leaching of Fully Radioactive High-level Waste Glass

Author:

Publisher:

Published: 1978

Total Pages:

ISBN-13:

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As part of continuing Department of Energy (DOE)-sponsored studies in waste management, the Pacific Northwest Laboratory (PNL) has been conducting the High-Level Waste Immobilization Program. The purpose of this program is to develop and demonstrate technology for incorporating nuclear wastes into final waste forms. The preparation and leach testing of fully radioactive, zinc borosilicate glass, which was prepared from power reactor waste, are described. Leach testing using the International Atomic Energy Association (IAEA) procedure was performed in deionized water for a period of 1.75 years. Leach rates were determined for activation products, fission products, and actinides. These rates ranged from 4 x 10−5 g of glass/cm2-day, based on cesium, to 4 x 10−9 g of glass/cm2-day, based on cerium. Following is the ranking of the release rates of the elements, from highest to lowest: Cs> Sr> Co> Sb> Mn> Pu> Eu> Rh> Cm> Ce. A similar leach test, using the same glass composition but with nonradioactive elements, has recently been completed. The leach rates of Cs and Sr for the nonradioactive glass were found to be in close agreement with those in this study. Slopes calculated from curves of cumulative fractions leached show that radioisotope release begins with a diffusion-type mechanism and changes gradually to a silicate lattice alteration mechanism. Changes in sampling frequency altered the apparent release mechanism when leachant changes were longer than one month. The leach rates were quite constant for samples taken from the top to the bottom of the glass melt, indicating a homogeneous product. Safety assessment studies and modeling programs use leach rates to predict the amount of radioactive material released should the waste be contacted by aqueous solutions. Further tests, focusing on geologic storage conditions and using fully radioactive wastes, are planned.

New Developments in Glassy Nuclear Wasteforms
New Developments in Glassy Nuclear Wasteforms

Author: Michael I. Ojovan

Publisher: Nova Publishers

Published: 2007

Total Pages: 152

ISBN-13: 9781600217838

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Based on the authors' recent investigations, this book describes the application of glassy and polyphase composite materials for nuclear waste immobilisation. It introduces immobilisation issues beginning with a short description of nuclear waste types and compositions. Sources of nuclear waste are described including the nuclear fuel cycle, operational and spent nuclear fuel reprocessing waste streams. The glassy waste forms currently being used for high-, intermediate- and low level radioactive waste immobilisation are described. Problems related to immobilisation capacity, process efficiency and long-term radionucleide retention are highlighted. Scientific and technical problems in nuclear waste immobilisation are emphasised in particular long-term waste form stability and durability. Recent developments in advanced nuclear waste forms are described such as glass composite materials (GCM) with higher versatility and waste loading. New immobilisation approaches and technologies are described including advanced cold crucible induction melting (CCM), self sustaining thermochemical immobilisation (SSI), and in-situ self-sintering in deep underground repositories. Long-term durability tests of nuclear waste glasses are outlined and the role of ion-exchange phase in glass corrosion is described in detail.

Waste Immobilization in Glass and Ceramic Based Hosts
Waste Immobilization in Glass and Ceramic Based Hosts

Author: Ian W. Donald

Publisher: John Wiley & Sons

Published: 2010-04-01

Total Pages: 526

ISBN-13: 1444319361

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The safe storage in glass-based materials of both radioactiveand non-radioactive hazardous wastes is covered in a single book,making it unique Provides a comprehensive and timely reference source at thiscritical time in waste management, including an extensive andup-to-date bibliography in all areas outlined to waste conversionand related technologies, both radioactive and non-radioactive Brings together all aspects of waste vitrification, drawscomparisons between the different types of wastes and treatments,and outlines where lessons learnt in the radioactive waste fieldcan be of benefit in the treatment of non-radioactive wastes