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Immobilization Of Simulated High Level Radioactive Waste In Borosilicate Glass
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Book Synopsis Immobilization of Simulated High-level Radioactive Waste in Borosilicate Glass by :
Download or read book Immobilization of Simulated High-level Radioactive Waste in Borosilicate Glass written by and published by . This book was released on 1991 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Integrated DWPF Melter System (IDMS), operated by the Savannah River Laboratory, is a pilot scale facility used in support of the start-up and operation of the Department of Energy's Defense Waste Processing Facility. The IDMS has successfully demonstrated, on an engineering scale (one-fifth), that simulated high level radioactive waste (HLW) sludge can be chemically treated with formic acid to adjust both its chemical and physical properties, and then blended with simulated precipitate hydrolysis aqueous (PHA) product and borosilicate glass frit to produce a melter feed which can be processed into a durable glass product. The simulated sludge, PHA and frit were blended, based on a product composition program, to optimize the loading of the waste glass as well as to minimize those components which can cause melter processing and/or glass durability problems. During all the IDMS demonstrations completed thus far, the melter feed and the resulting glass that has been produced met all the required specifications, which is very encouraging to future DWPF operations. The IDMS operations also demonstrated that the volatile components of the melter feed (e.g., mercury, nitrogen and carbon, and, to a lesser extent, chlorine, fluorine and sulfur) did not adversely affect the melter performance or the glass product.
Book Synopsis Waste Immobilization in Glass and Ceramic Based Hosts by : Ian W. Donald
Download or read book Waste Immobilization in Glass and Ceramic Based Hosts written by Ian W. Donald and published by John Wiley & Sons. This book was released on 2010-04-01 with total page 526 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Book Synopsis Report on the High-level Nuclear Waste Immobilization Program by : United States. Department of Energy. Office of Inspector General
Download or read book Report on the High-level Nuclear Waste Immobilization Program written by United States. Department of Energy. Office of Inspector General and published by . This book was released on 1982 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Book Synopsis Volatility of a Zinc Borosilicate Glass Containing Simulated High-level Radioactive Waste by : Walter James Gray
Download or read book Volatility of a Zinc Borosilicate Glass Containing Simulated High-level Radioactive Waste written by Walter James Gray and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Characterisation and Interaction of Simulated High Level, Radioactive Waste (HLW) with Borosilicate Glass by : Suzy Morgan
Download or read book Characterisation and Interaction of Simulated High Level, Radioactive Waste (HLW) with Borosilicate Glass written by Suzy Morgan and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Immobilization of Radioactive Waste in Glass Matrices by :
Download or read book Immobilization of Radioactive Waste in Glass Matrices written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A promising process for long-term management of high-level radioactive waste is to immobilize the waste in a borosilicate glass matrix. Among the most important criteria characterizing the integrity of the large-scale glass-waste forms are that they possess good chemical stability (including low leachability), thermal stability, mechanical integrity, and high radiation stability. Fulfillment of these criteria ensures the maximum margin of safety of glass-waste products, following solidification, handling, transportation, and long-term storage.
Book Synopsis Characterisation and Interaction of Simulated High Level, Radioactive Waste (HLW) with Borosilicate Glass by :
Download or read book Characterisation and Interaction of Simulated High Level, Radioactive Waste (HLW) with Borosilicate Glass written by and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Volatility of a Zinc Borosilicate Glass Containing Simulated High-level Radioactive Waste. [800 to 1200°C]. by :
Download or read book Volatility of a Zinc Borosilicate Glass Containing Simulated High-level Radioactive Waste. [800 to 1200°C]. written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Volatilities of a zinc borosilicate glass containing 25 wt. percent simulated high-level radioactive waste calcine and of the calcine itself were determined in the range 800 to 1200°C. The fission products Rb, Mo, Ru, Te, and Cs were detected in the vapor from both the glass and the calcine. In general, the vaporization rates were lower from the glass with the exception of Rb and Cs at 1200°C, where the rates were about the same from the glass as from the calcine. Furthermore, slopes of Arrhenius plots for Rb and Cs were higher for the glass indicating that more of these elements would be lost from the glass above 1200°C than from the calcine. Vaporization of all volatile elements from the glass seems to be dominated by a single mechanism; thus, vapor composition over the glass is essentially temperature independent. Several mechanisms apply to vaporization of the various elements from the calcine. Gross weight-loss from the glass and calcine appears to be surface and diffusion controlled, respectively.
Book Synopsis Glass as a Waste Form and Vitrification Technology by : National Research Council
Download or read book Glass as a Waste Form and Vitrification Technology written by National Research Council and published by National Academies. This book was released on 1997-03-02 with total page 182 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Code for Air Raid Shelters, Buildings and Mines by :
Download or read book Code for Air Raid Shelters, Buildings and Mines written by and published by . This book was released on 1942* with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Deposition of vapour from borosilicate glass containing simulated high-level radioactive wastes by : H. Yamanaka
Download or read book Deposition of vapour from borosilicate glass containing simulated high-level radioactive wastes written by H. Yamanaka and published by . This book was released on 1983 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radioactive Waste Forms for the Future by : Werner Lutze
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 High-level Radioactive Wastes written by and published by . This book was released on 1982 with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis High-level Nuclear Waste Borosilicate Glass by :
Download or read book High-level Nuclear Waste Borosilicate Glass written by and published by . This book was released on 1992 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Regulatory Aspects of Borosilicate Glass High-Level Waste Forms the Process, the Product and the Disposal by :
Download or read book Regulatory Aspects of Borosilicate Glass High-Level Waste Forms the Process, the Product and the Disposal written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Immobilization of high-level radioactive waste (HLW) in borosilicate glass is acknowledged world-wide as an acceptable method for preparing HLW for geologic disposal. A waste acceptance process is underway in the United States that will provide specifications and procedures for waste producers well in advance of the availability of a federal repository. Extensive experimental data and rigorous quality assurance and control for plant operation are expected to provide convincing evidence that borosilicate glass waste forms produced in the vitrification plants meet the specifications and can be disposed of safely in a geologic repository.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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