Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site (2001) / Chapter Skim
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Appendix B: Interim Report
Appendix B: Interim Report
Pages 40-76
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APPENDIX B Interim Report 40
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Waste at the Savannah River Site Board on Radioactive Waste Management Board on Chemical Sciences and Technology Division on Earth and Life Studies National Research Council NATIONAL ACADEMY PRESS Washington, D.C.
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42 R&D on a Salt Processing al lterrzat~ve for HL W at the Savannah River Site NATIONAL ACADEMY PRESS 2101 Constitution Avenue, N.W. Washington, D.C.
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Functioning in accordance with general policies determined by the Academy, the Council has become the principal operating agency of both the National Academy of Sciences and the National Academy of Engineering in providing services to the government, the public, and the scientific and engineering communities. The Council is administered jointly by both Academies and the Institute of Medicine.
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ANDREWS, Senior Staff Officer, Board on Radioactive Waste Management CHRISTOPHER K MURPHY, Program Officer, Board on Chemical Sciences and Technology LAURA LLANOS, Senior Project Assistant, Board on Radioactive Waste Management TONI GREENLEAF, Administrative Associate, Board on Radioactive Waste Management
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STEWDLER, Argonne National Laboratories (retired) , Argonne, Illinois ATSUYUKI SUZUKI, University of Tokyo, Japan JOHN J
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KELLER II, Union Carbide Company (retired) , South Charleston, West Virginia SANGTAE KIM, Eli Lilly and Company, Indiar~apolis, Indiana WILLIAM KLEMPERER, Harvard University, Cambridge, Massachusetts THOMAS J
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Appendix B Interim Report 47 Acknowledgement of Reviewers This report has been reviewed in draPc fonn by individuals chosen for their diverse perspectives and technical expertise, in accordance with procedures approved by the National Research Council (NRC)
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Waste Salt Processing at the Savannah River Site, was issued in August 2000. DOE subsequently asked the National Research Council to provide an assessment of DOE's efforts to select a processing alternative for removal of cesium, strontium, and actinides from high level waste at the Savannah River Site.
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Waste Salt Processing at the Savannah River Site (National Research Council, 20001. After receiving that report, DOE asked the NRC to provide additional advice on the waste processing efforts at the SRS, and a new committee was impax~eled to examine the DOE's selection of a process for separating radionuclides from soluble high-level radioactive waste at that site.
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program for three of the four alternative processing options (small tank precipitation using TPB, crystalline silicotitanate ion exchange, and caustic side solvent extraction, each including monosodium titanate processingfor removing strontium and actinides) until enough information is available to make a more defensible and transparent downselection decision.
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This representative recommends to the DOE Assistant Secretary for Environmental Management the final determination on the downselection outcome.
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2. Project cost reduction potential—Potential that cost savings in the total project cost can be identified (generally due to flow sheet or equipment arrangement changes that would allow facility foot~nnt reductions)
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communication, January 5, 2001. In recognition of some commonalties, the eleven criteria for process selection were grouped by the TEA under the set of six goals shown in Box 2.
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The TEA employed a series of steps to develop and implement the ss proposed cntena. in particular, they used several groups of experts to carry out preliminary application of the enters to evaluation of the three processing alternatives.
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In all of the exercises the resulting total scores for the three alternative processes all fell within the range of 0 60 to 0.69; in one exercise the identical total score of 0.63 was calculated for all three alternative processes. The actual scoring and weightings were consensus values arrived at in review meetings among the experts following extensive discussion.
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Any process selected for implementation would need to gain the necessary regulatory approval, which will be a clear "yes/no" decision. While it is an appropriate goal for each of the alternative processes to minimize radioactive and chemical emissions and generation of secondary waste, the process to be selected will either meet regulatory approval or it will not.
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Finding: The committee finds that DOE's proposed criteria are an acceptable basis for selecting among the candidate processes under consideration; however, as noted in the preceding discussion, some of the criteria Lo not appear to be independent of others and some criteria appear unlikely to discriminate among the process alternatives. The use of the criteria to reach a final decision relies on a methodology that is still evolving.
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The final selection of a process for treating the SRS high-level waste will be a management decision. The final decision rests with the Assistant Secretary of Energy for Environmental Management and will be made on the basis of documentation related to the eleven criteria discussed here.
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Waste Salt Processing at the Savannah River Site. Washington, D.C.: National Academy Press, 142pp.
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Mr. Levenson has served on many National Research Council committees, and in 1998 served as principal investigator for the Board on Radioactive Waste Management project on aluminum spent fuel.
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His research, which fathered synthetic macrocyclic ligand chemistry and created the molecular template effect, is presently focused on homogeneous catalysis, bioinorgan~c chemistry, and orderly molecular entanglements. He is a recipient of the American Chemical Society's Award for Distinguished Service in Inorganic Chemistry and its Award for Research in Inorganic Chemistry.
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He chaired both the Matenals Review Board for the DOE Office of Civilian Radioactive Waste Management and the U.S. Nuclear Regulatory Commission Advisory Committee on Nuclear Waste.
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64 R&D on a Salt Processing Alternative for HLWat the Savannah River Site Steindler has served on several National Research Council committees, and currently serves on the Board on Radioactive Waste Management.
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Appendix B.: Interim Report APPENDIX B LETTERS OF REQUEST FOR THIS STUDY 65
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Crowley: would like to take this opportunity to thank you and your Committee Members for your extraordinary effort providing the Department with an independent technical review of alternatives for processing the high-level radioactive waste salt solutions at the Savannah River Site. We agree with your interim comments noting that additional research and development is required for each option, and we are proceeding with addressing your comments in our research and development plans for fiscal years 2000 and 2001.
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Fret Deputy Assistant Secretary for Project Completion Office of Project Completion Enclosure cc: M Gilbertson, EM-52 K
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20007 Dear Dr. Crowley: Department of Energy Washington, DC 20585 June 15, 2000 Thank you for your May 16, 2000, letter responding to my request that the National Research Council continue its support of the Department's high-level waste salt processing alternatives at the Savannah River Site.
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Sincerely, 69 , ~ :'t'6: Mark W Frei Deputy Assistant Secretary for Project Completion Of lice of Environmental Management cc: M
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TANK WASTE PROCESSING DOE has the responsibility for waste management at SRS and has implemented a program to stabilize this HEW and close the tank farms. The tank waste processing system at SRS comprises the major components; (a)
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The saltcake and sludge contain substantial quantities of supemate within their mass; this interstitial supernate corresponds to about half of the total supernate in the tarlks. Radionuclide Immobilization The Defense Waste Processing Facility (DWPF)
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Some of these waste streams are recycled back to the tanks, some are recycled within the venous processing operations, and yet other wastes are treated and stabilized for burial. Most notably, the "decontaminated" salt supernate (i.e., the solutions remaining after actinide, strontium, and cesium removal)
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~ September ~ 995, SRS initiated ITP processing operations in a tank that contained about I.7 million liters (450,000 gallons) of salt solutions.
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In most applications the separated ions are etudes from the ion exchange matenal, e.g., using a dilute acid, the eluted ions are concentrated, and the ion exchanger is reused over and over. Although this technology is well established, ion exchange for cesium removal from high-level waste at SRS and other DOE sites poses challenges.
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This history includes long periods of time in which solvents of venous organic species have been exposed to high-radiation fields without experiencing catastrophic degradation rates. Solvent extraction operations usually consist of selectively transferring components from an aqueous, acidic stream into the organic stream.
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76 R&D on a Salt Processing Alternative for HLWat the Savannah River Site been demonstrated at the site for less radioactive salt solutions, the degree of retention of cesium may not satisfy regulatory requirements.
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