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Suggested Citation:"Appendix D: Information-Gathering Meetings." National Research Council. 2001. Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site. Washington, DC: The National Academies Press. doi: 10.17226/10170.
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Page 81

APPENDIX D

Information-Gathering Meetings

PRESENTATIONS GIVENT DURING SECOND COMMITTEE MEETING

February 13 - February 14, 2001, Augusta, Georgia

Salt Processing Technology Development Overview (Harry Harmon, SRS)

Alpha and Strontium Removal: Program Overview (Samuel Fink, SRS)

Alpha and Strontium Removal: Sorbent Studies (David Hobbs, SRS)

Alpha and Strontium Removal: Solid-Liquid Separation Studies (Michael Poirier, SRS)

Caustic Side Solvent Extraction: Overview (Major Thompson, SRS)

CSSX: Flowsheet Test Results (Ralph Leonard, ANL)

CSSX: Solvent Chemical and Physical Properties (Bruce Moyer, ORNL)

CSSX: Solvent Chemical and Thermal Stability (Bruce Moyer, ORNL)

CSSX: Solvent Radiolytic Stability (Leon Klatt, ORNL)

CSSX: Radioactive Waste Tests (Doug Walker, SRTC)

CSSX: Solvent Preparation and Commercialization (Peter Bonnesen, ORNL)

Crystalline Silicotitanate Nonelutable Ion Exchange: Overview (Dennis Wester, PNNL)

CST: Gas Generation (Dennis Wester, PNNL)

Suggested Citation:"Appendix D: Information-Gathering Meetings." National Research Council. 2001. Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site. Washington, DC: The National Academies Press. doi: 10.17226/10170.
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Page 82

CST: Chemical and Thermal Stability (Doug Walker, SRTC)

CST: Chemical and Thermal Stability Studies of Cesium-Loaded IE-911 (Liyu Li, PNNL)

CST: Pretreatment Technologies for IE-911 Development (Jim Krumhansl, SNL)

CST: Performance of IE-911: Characterization of As-Received, NaOH-Treated, and Simulant-Treated CST (May Nyman, SNL)

CST: Effect of Organic Impurities and Minor Components on Cesium Sorption (Fernando Fondeur, SRTC)

CST: Sorbent Handling and Sampling (Frank Smith, SRTC)

Small Tank Tetraphenylborate Precipitation: Overview (Joe Walker ORNL)

STTP: Tetraphenylborate Decomposition and Catalyst Studies (Mark Barnes, SRTC)

STTP: NMR Studies for Catalyst Understanding (Peter Bonneson, ORNL)

STTP: Characterization of Palladium and Mercury after Reaction with Dissolved Tetraphenylboron (Martine Duff, University of Georgia)

STTP: Catalyst Development Overview (Jim Boncella, University of Florida)

STTP: Antifoam Development and Testing (Dan Lambert, SRTC)

STTP: Real Waste Tests (Mark Barnes, SRTC)

STTP: 20-Liter Continuous Stirred Tank Reactor Studies (Doug Lee, ORNL)

Suggested Citation:"Appendix D: Information-Gathering Meetings." National Research Council. 2001. Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site. Washington, DC: The National Academies Press. doi: 10.17226/10170.
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Page 83

PRESENTATIONS GIVEN DURING THE THIRD COMMITTEE MEETING

March 26-27, 2001, Washington, D.C.

High-Level Waste Characterization (Joe Carter, SRS)

Salt Processing Project Technology Development Update (Harry Harmon, SRS)

Suggested Citation:"Appendix D: Information-Gathering Meetings." National Research Council. 2001. Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site. Washington, DC: The National Academies Press. doi: 10.17226/10170.
×
Page 81
Suggested Citation:"Appendix D: Information-Gathering Meetings." National Research Council. 2001. Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site. Washington, DC: The National Academies Press. doi: 10.17226/10170.
×
Page 82
Suggested Citation:"Appendix D: Information-Gathering Meetings." National Research Council. 2001. Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site. Washington, DC: The National Academies Press. doi: 10.17226/10170.
×
Page 83
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 Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site
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The U.S. Department of Energy (DOE) is nearing a decision on how to process 30 million gallons of high-level radioactive waste salt solutions at the Savannah River Site in South Carolina to remove strontium, actinides, and cesium for immobilization in glass and eventual shipment to a geologic repository. The department is sponsoring research and development (R&D) work on four alternative processes and plans to use the results to make a downselection decision in a June 2001 time frame. The DOE requested that the National Research Council help inform this decision by addressing the following charge:

  1. evaluate the adequacy of the criteria that will be used by the department to select from among the candidate processes under consideration;
  2. evaluate the progress and results of the research and development work that is being undertaken on these candidate processes; and
  3. assess whether the technical uncertainties have been sufficiently resolved to proceed with downsizing the list of candidate processes.

Responses to the last two points are provided in this report. Research and Development on a Salt Processing Alternative for High-Level Waste at the Savannah River Site focuses exclusively on the technical issues related to the candidate processes for radionuclide removal from high-level waste salt solutions at SRS. The committee's interim report served as a response to the first point of this charge, and may be read in Appendix B. In that report, the committee found that DOE's proposed criteria are an acceptable basis for selecting among the candidate processes under consideration, but that the criteria should not be implemented in a way that relies on a single numerical "total score."

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