Waste Forms Technology and Performance Final Report (2011) / Chapter Skim
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Appendix C: Interim Report
Appendix C: Interim Report
Pages 255-284
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Appendix C Interim Report 255
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257 APPENDIX C Waste Forms Technology and Performance INTERIM REPORT Committee on Waste Forms Technology and Performance Nuclear and Radiation Studies Board Division on Earth and Life Studies THE NATIONAL ACADEMIES PRESS Washington, D.C.
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258 APPENDIX C THE NATIONAL ACADEMIES PRESS 500 Fifth Street, N.W. Washington, DC 20001 NOTICE: The project that is the subject of this report was approved by the Governing Board of the National Research Council, whose members are drawn from the councils of the National Academy of Sciences, the National Academy of Engineering, and the Institute of Medicine.
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259 APPENDIX C The National Academy of Sciences is a private, nonprofit, self-perpetuating society of distinguished scholars engaged in scientific and engineering research, dedicated to the furtherance of science and technology and to their use for the general welfare. Upon the authority of the charter granted to it by the Congress in 1863, the Academy has a mandate that requires it to advise the federal government on scientific and technical matters.
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1 Potential modifications of waste form production methods that may lead to more efficient production of waste forms that meet their performance requirements. Potential new waste forms that may offer enhanced performance or lead to more efficient production.
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Accelerating schedules for treating and immobilizing HLW by introducing new and/or improved waste forms and processing technologies could also accelerate tank waste retrieval and closure schedules. The committee used its expert judgment to identify the opportunities described in this report.
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The committee will not make recommendations on applications of particular production methods or waste forms to specific EM waste streams. A major focus of the DOE-EM cleanup program is on retrieving legacy wastes resulting from nuclear weapons production and testing and processing them into waste forms suitable for disposal in onsite or offsite facilities.
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There have been numerous recent reports on the development of waste forms and processing technologies for advanced nuclear fuel cycles; some examples are given in Attachment D Examples of these technologies include: Waste form materials designed for significantly higher waste loadings or for improved performance in specific disposal environments.
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WASTE FORM AND PROCESSING OPPORTUNITIES The committee has identified four opportunities consistent with its statement of task (Box 2) : Production of crystalline ceramic 5 waste forms using fluidized bed steam reforming Production of glass, glass composite, and crystalline ceramic waste forms using cold crucible induction melters Production of glass, glass composite, and crystalline ceramic waste forms using hot isostatic pressing Evaluation of the long-term durability of new waste form materials using experimental studies, laboratory tests, and model development 3 A waste stream is referred to as orphan when it has no clear-cut disposition pathway.
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Its primary advantages are high throughput and ability to accommodate a wide range of feeds and additives, including feeds containing anionic sulfur and nitrogen species, halides, and organics that are incompatible with some other types of waste forms and waste form production processes. FBSR is based on fluidized bed technology, which was invented in the 19th century and found widespread use in the refining and chemical industries starting around World War II.
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and increased production rates of high-activity and low-activity waste forms. For processing waste streams, including resins, containing large quantities of organic materials and nitrates.
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Cold Crucible Induction Melter Technology The Cold Crucible Induction Melter (CCIM) is a promising technology for producing glass, glass composite, and crystalline ceramic waste forms.
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Its deployment in DOE-EM applications may require some up-front development work to ensure its compatibility with specific process flowsheets, but no basic research is likely to be required. Because CCIMs are smaller per unit of throughput and operationally more robust than JHMs, they could potentially be back-fitted to the Defense Waste Processing Facility at Savannah River and the Waste Treatment Plant at Hanford.
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Notably, it produces monolithic waste forms with substantially reduced volumes compared to untreated waste streams. Because the waste is processed in a sealed can, there are no volatile emissions.
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Although HIP is a flexible technology it does have some limitations. Crystalline ceramic waste forms produced by HIP (as well as conventional press and sinter technology)
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Understanding the long-term durability of waste forms can provide valuable information for higher-level safety analyses of disposal systems.
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In the committee's judgment, assessment of the long-term durability of crystalline ceramic waste forms represents a key near-term opportunity for DOE-EM. Crystalline ceramic materials produced, for example, by FBSR and HIP have been identified elsewhere in this interim report as flexible waste forms with many potential applications, including high-activity and low activity waste immobilization.
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The committee's final report will address the statement of task in its entirety. It will provide a more detailed assessment of waste forms, processing technologies, and state-of-the-art tests and models.
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mineralization for high organic and nitrate waste streams for the Global Nuclear Energy Partnership (GNEP) , Waste Management ‘08, Paper #8314.
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2006. Tank Waste Retrieval, Processing, and On-Site Disposal at Three Department of Energy Sites.
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JANTZEN, Savannah River National Laboratory, Aiken, South Carolina DAVID W JOHNSON, JR, Bells Labs (retired)
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, France Cementatious waste forms and barriers 9:00–9:30 am Fred Glasser, University of Aberdeen, UK Combined inert matrix fuels and related waste forms 9:30-10:00 am Claude Degueldre, Paul Sheerer Institute, Switzerland Break 10:00-10:30 am Ceramic and phosphate glass waste forms and cold crucible 10:30-11:00 pm technology Sergey Stefanovsky, SIA Radon, Russia Overview of CEA's and French initiatives related to waste forms 11:00-11:30 pm Etienne Vernaz, Commissariat à l'Énergie Atomique, France Overview of Australia/ANSTO initiatives related to waste forms 11:30-12:00 pm Kath Smith and Bruce Begg, Australian Nuclear Science and Technology Organisation (ANSTO) , Australia Lunch 12:00-1:00 pm Session II: Select Domestic Issues Computational methods applied to the design and evaluation of 1:00–1:30 am waste forms Bill Weber, Pacific Northwest National Laboratory
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Yvette Collazo 278 15, 2010 June APPENDIX C Page 19 Overview of waste forms and near-field interactions in a 1:30-2:00 pm performance assessment perspective Carl Steefel, Lawrence Berkeley National Laboratory Matching waste forms to waste processing strategies 2:00-2:30 pm Mark Peters, Argonne National Laboratory Impact of waste forms on overall repository performance 2:30-3:00 pm assessment Peter Swift, Sandia National Laboratories Break 3:00-3:15 pm Overview of the Vitreous State Laboratory and geopolymer 3:15-3:45 pm development Ian Pegg and Werner Lutze, Catholic University of America Cementitious Barriers Partnership 3:45-4:15 pm David Kosson, Vanderbilt University Industry perspectives on potential waste forms from recycling 4:15-4:45 pm Rod McCullum, Nuclear Energy Institute Panel discussion 4:45-5:15 pm All participants Adjourn 5:15 pm
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Basic Research Needs for Advanced Nuclear Energy Systems, July 31- August 3, 2006 (see the panel #5 report on advanced waste forms)
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The first one operates in a reducing environment and its function is to evaporate the liquid nuclear waste stream; destroy organics; reduce nitrates, nitrites, and nitric acid to nitrogen gas; and form a stable solid waste product. The first stage fluidized bed of the FBSR process is referred to as the Denitration and Mineralization Reformer, or DMR.
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Thus, FBSR waste forms can be useful for immobilizing these species to prevent their leaching into groundwater. Other minerals in the sodalite family, namely hauyne and lazurite which are also cage structured minerals, can accommodate either (SO4=)
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. These cage-structured sodalites were minor phases in HLW supercalcine waste forms and were found to retain Cs, Sr, and Mo into the cage-like structure, e.g., Mo as Na6[Al6Si6O24]
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The size of these systems is limited only by the replacement crane capacity since all the structural support is provided by a stainless steel shell which contains the refractory. The Defense Waste Process Facility at Savannah River Site is the largest production melter of this type ever built.
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, Mid-Atlantic Technology, Research and Innovation Center Alexandra Navrotsky (NAS) , University of California, Davis Alfred Sattelberger, Argonne National Laboratory Carl Steefel, Lawrence Berkeley National Laboratory Etienne Vernaz, CEA, Nuclear Energy Division, Marcoule Raymond Wymer, Oak Ridge National Laboratory (retired)
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