Leaching of Actinide-doped Nuclear Waste Glass in a Tuff-dominated System

Leaching of Actinide-doped Nuclear Waste Glass in a Tuff-dominated System

Author:

Publisher:

Published: 1987

Total Pages: 14

ISBN-13:

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A laboratory leaching test has been performed as part of a project to evaluate the suitability of tuff rocks at Yucca Mountain, Nevada, as a site for a high-level nuclear waste repository. Glass samples were placed in water inside tuff vessels, and then the tuff vessels were placed in water inside Teflon containers. Glass-component leach rates and migration through the tuff were measured for samples of the ATM-8 actinide glass, which is a PNL 76-68 based glass doped with low levels of 99Tc, 237Np, 238U, and 239Pu to simulate wastes. Disc samples of this glass were leached at 90°C for 30, 90, and 183 days inside tuff vessels using a natural groundwater (J-13 well-water) as the leachant. At the end of each leaching interval, the J-13 water present inside and outside the rock vessel was analyzed for glass components in solutions. Boron, molybdenum, and technetium appear to migrate through the rock at rates that depend on the porosity of each vessel and the time. The actinide elements were found only in the inner leachate. Normalized elemental mass loss values for boron, molybdenum, and technetium were calculated using concentrations of the inner and outer leachates and assuming a negligible retention on the rock. The maximum normalized release was 2.3 g/m2 for technetium. Boron, molybdenum, technetium, and neptunium were released linearly with respect to each other, with boron and molybdenum released at about 85% of the technetium rate, and neptunium at 5 to 10% of the technetium rate. Plutonium was found at low levels in the inner leachate but was strongly sorbed on the steel and Teflon supports. Neptunium was sorbed to a lesser extent. 8 refs., 6 figs., 6 tabs.


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


Waste Forms Technology and Performance

Waste Forms Technology and Performance

Author: National Research Council

Publisher: National Academies Press

Published: 2011-09-05

Total Pages: 308

ISBN-13: 0309187338

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The Department of Energy's Office of Environmental Management (DOE-EM) is responsible for cleaning up radioactive waste and environmental contamination resulting from five decades of nuclear weapons production and testing. A major focus of this program involves the retrieval, processing, and immobilization of waste into stable, solid waste forms for disposal. Waste Forms Technology and Performance, a report requested by DOE-EM, examines requirements for waste form technology and performance in the cleanup program. The report provides information to DOE-EM to support improvements in methods for processing waste and selecting and fabricating waste forms. Waste Forms Technology and Performance places particular emphasis on processing technologies for high-level radioactive waste, DOE's most expensive and arguably most difficult cleanup challenge. The report's key messages are presented in ten findings and one recommendation.


Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries XI

Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries XI

Author: Connie C. Herman

Publisher: John Wiley & Sons

Published: 2012-04-11

Total Pages: 247

ISBN-13: 1118407962

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This proceedings contains papers presented at the Ceramic/Glass Science and Technology for Nuclear and Environmental Industries symposium. Topics include nuclear and environmental technology applications in the ceramic industry; nuclear waste forms and fuels processing and technology - ceramic forms; nuclear waste forms processing and technology - steam reforming; panel discussion on nuclear waste forms durability, testing, and disposal status; nuclear waste forms and fuels processing and technology - glass forms; and advances in nuclear waste form testing and characterization methods.


Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IX

Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IX

Author: John D. Vienna

Publisher: John Wiley & Sons

Published: 2012-04-05

Total Pages: 384

ISBN-13: 1118407024

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In today's world of increasingly stringent environmental regulations, it is critical to identify and adequately address environmental issues in the ceramic industry to ensure success. In addition, ceramics and glasses play a critical role in the nuclear industry. Nuclear fuels and waste forms for low-level and high-level radioactive, mixed, and hazardous wastes are primarily either ceramic of glass. Effective and responsible environmental stewardship is becoming increasingly more important in the world. These proceedings detail the results of the ongoing effort in these areas. Proceedings of the symposium held at the 105th Annual Meeting of The American Ceramic Society, April 27-30, in Nashville, Tennessee; Ceramic Transactions, Volume 155.


Environmental Issues and Waste Management Technologies in the Materials and Nuclear Industries XII

Environmental Issues and Waste Management Technologies in the Materials and Nuclear Industries XII

Author: Alex Cozzi

Publisher: John Wiley & Sons

Published: 2009-09-24

Total Pages: 322

ISBN-13: 0470538368

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This book documents a special collection of articles from a select group of invited prominent scientists from academia, national laboratories and industry who presented their work at the symposia on Environmental and Energy Issues at the 2008 Materials Science and Technology (MS&T’08) conference held in Pittsburgh, PA. These articles represent a summary of the presentations focusing on topics in nuclear, environmental, and green engineering were held, including a discussion of Waste Glass Leach Testing and Modeling.


Leaching Savannah River Plant Nuclear Waste Glass in a Saturated Tuff Environment

Leaching Savannah River Plant Nuclear Waste Glass in a Saturated Tuff Environment

Author:

Publisher:

Published: 1984

Total Pages: 19

ISBN-13:

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Samples of SRP glass containing either simulated or actual radioactive waste were leached at 90°C under conditions simulating a saturated tuff repository environment. The leach vessels were fabricated of tuff and actual tuff groundwater was used. Thus, the glass was leached only in the presence of those materials (including the Type 304L stainless steel canister material) that would be in the actual repository. Tests were performed for time periods up t 6 months at a SA/V ratio of 100 m−1. Results with glass containing simulated waste indicated that stainless steel canister material around the glass did not significantly affect the leaching. Based on Li and B (elements not in significant concentrations in the tuff or tuff groundwater), glass containing simulated waste leached identically to glass containing actual radioactive waste. The tuff buffered the pH so that only a slight increase was observed as a result of leaching. Results with glass containing actual radioactive waste indicated that tuff reduced the concentrations of Cs-137, Sr-90, and Pu-238 in the free groundwater in the simulated repository by 10 to 100X. Also, radiolysis of the groundwater by the glass (approximately 1000 rad/h) did not significantly affect the pH in the presence of tuff. Measured normalized mass losses in the presence of tuff for the glass based on Cs-137, Sr-90, and Pu-238 in the free groundwater were extremely low, nominally 0.02, 0.02, and 0.005 g/m2, respectively, indicating that the glass-tuff system retained radionuclides well. 9 references, 2 figures, 3 tables.