Immobilization of Simulated High-level Radioactive Waste in Borosilicate Glass

Immobilization of Simulated High-level Radioactive Waste in Borosilicate Glass

Author:

Publisher:

Published: 1991

Total Pages: 14

ISBN-13:

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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.


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


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.


Immobilization of Radioactive Waste in Glass Matrices

Immobilization of Radioactive Waste in Glass Matrices

Author:

Publisher:

Published: 1978

Total Pages:

ISBN-13:

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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.


Volatility of a Zinc Borosilicate Glass Containing Simulated High-level Radioactive Waste. [800 to 1200°C].

Volatility of a Zinc Borosilicate Glass Containing Simulated High-level Radioactive Waste. [800 to 1200°C].

Author:

Publisher:

Published: 1976

Total Pages:

ISBN-13:

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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.