Items in cart [0] Questions? Call 888-624-8373

PAPERBACK + PDF your price: $34.00 add to cart PAPERBACK list:$29.00 Web:$26.10 add to cart PDF BOOK your price: $22.50 add to cart Rights & Permissions Free Resources PDF EXECUTIVE SUMMARY Display this book on your site! Related Titles Going the Distance? The Safe Transport of Spent Nuclear Fuel and High-Level Radioactive Waste in the United States Risk and Decisions About Disposition of Transuranic and High-Level Radioactive Waste Other Related Titles Evaluation of the U.S. Department of Energy's Alternatives for the Removal and Disposition of Molten Salt Reactor Experiment Fluoride Salts (1997) Commission on Geosciences, Environment and Resources (CGER) Web Search Builder Use this book's key terms to search within this book, across our collection, or across the Web. Skim This Chapter Skim this chapter and use this chapter's key terms to search within this book. Reference Finder Paste in your own text to find books that relate to your topic. Page 89   E-mail  Facebook  Digg  Stumble  Twitter More Page 89 Front Matter (R1-R14) Executive Summary (1-9) 1 Introduction (10-22) 2 Radiolysis and Nuclear Reactions (23-36) 3 Fluoride Salt Chemistry, Partitioning, and System Corrosion (37-44) 4 Preferred Technical Approach (45-49) 5 Comments on Specific Separation Technologies (50-57) 6 Nuclear Criticality Considerations (58-64) 7 Strategic Alternatives (65-71) 8 Management of MSRE Hazards (72-78) 9 Summary and Responses to Questions in Statement of Task (79-88) References (89-92) Appendix A: List of Materials Reviewed (93-102) Appendix B: Alternative Fluorinating Agents (103-106) Appendix C: Contamination Concerns Relating to Radon Gas Spread (107-108) Appendix D: Use of a Nuclear Poison to Inhibit Nuclear Criticality (109-110) Appendix E: Hazard Scoping of Major Actions for Remediation (111-120) Appendix F: List of Acronyms and Abbreviations (121-122) Appendix G: Glossary (123-126) Appendix H: Biographical Sketches of Molten Salt Panel Members and Consultants (127-134)

Below are the first 10 and last 10 pages of uncorrected machine-read text (when available) of this chapter, followed by the top 30 algorithmically extracted key phrases from the chapter as a whole.
Intended to provide our own search engines and external engines with highly rich, chapter-representative searchable text on the opening pages of each chapter. Because it is UNCORRECTED material, please consider the following text as a useful but insufficient proxy for the authoritative book pages.

Do not use for reproduction, copying, pasting, or reading; exclusively for search engines.

OCR for page 89
References ANS-8.1 Working Group. 1993. Nuclear Criticality Safety in Operations with Fissile Materials Outside Reactors. ANSI/ANS-8.1-1983(R1988~. La Grange Park, Ill.: American Nuclear Society. Benedict, M., T. Pigford, and H. Levi. 1981. Nuclear Chemical Engineering. New York: McGraw-Hill, Inc. Crume, C. 1994. Nuclear Criticality Safety Issues Associated with Uranium Migration in the MSRE. Viewgraphs from presentation to the Independent Review Panel, Oak Ridge, Tenn. October 11. Eller, Phillip G., J. G. Maim, and R. A. Penneman. 1988. Method for fluorination of actinide fluorides and oxyfluorides thereof using O2F2. U.S. Patent No. 4,783,322, November. Frolov, V. V., B. G. Ryazanov, V. I. Sviridov, and G. S. Starodubtsev. 1995. A review of criticality accidents which occurred in the Russian industry. Pp. 23-30 in Proceedings of the Fifth International Conference on Nuclear Criticality, Albuquerque, N.Mex., September 17-21. Guymon, R. H. 1971. MSRE Procedures for the Period Between Examination and Ultimate Disposal (Phase III of the Decommissioning ProgramJ. ORNL/TM-3253. Oak Ridge, Tenn.: Union Carbide Corp., Oak Ridge National Laboratory. Hollenbach, D. F., and C. M. Hopper. 1994. Criticality Safety Study of the MSRE Fuel Drain Tank Cell in Building 7503. ORNL/TM-12642. Oak Ridge, Tenn.: Oak Ridge National Laboratory. Holmes, J. T., L. B. Koppel, J. D. Gabor, R. Devabhaktuni, and A. A. Jonke. 1969. Engineering-scale studies of the fluorination of uranium oxide with brominepentafluoride. Industrial Engineering Chemistry, Process Design and Development 8:43-51. Jarry, R. L., and M. J. Steindler. 1967. Reaction of gaseous brominepentafluoride with uranium compounds, I: The kinetics of the reactions with uranium tetrafluoride (UF4) and difluorodioxo uranium (UO2F24. Journal of Inorganic Nuclear Chemistry 29:1591-1597. Jarry, R. L., and M. J. Steindler. 1968. Reaction of gaseous brominepentafluoride with uranium compounds, II: Kinetics of the reaction with U3OS, uranium IV oxide and uranium VI oxide. Journal of Inorganic Nuclear Chemistry 30:127-132. Katz, J. J., and G. T. Seaborg. 1986. The Chemistry of the Actinide Elements, 2nd Ed. J. J. Katz, G. T. Seaborg, L. R. Morss, editors. New York: Chapman and Hall Ltd. Knief, R. A. 1985. Nuclear Criticality Safety Theory and Practice. La Grange Park, Ill.: American Nuclear Society. Knief, R. A. 1992. Nuclear Engineering: Theory and Technology of Commercial Nuclear Power. Washington, D.C.: Hemisphere Publishing Company. 89

OCR for page 90
9o AN EVALUATION OF DOE ALTERNATIVES FOR MSRE Lai, G. Y. 1990. High-Temperature Corrosion of Engineering Alloys. Materials Park, Ohio: ASM International. Liebenthal, J. L., M. G. Adamson, F. E. Harrington, T. P. McLaughlin, and R. E. Thoma. 1994. Independent Review Panel Report: Molten Salt Reactor Experiment Uranium Migration Remediation. Report to Martin Marietta Systems, Oak Ridge, Tenn.: Oak Ridge National Laboratory. Margrave, J. L., K. R. Kunze, R. H. Hauge, and D. Hamill. 1976. IR matrix study of reactions of UF4 with fluorine. Journal of Chemical Physics 65:2026. Margrave, J. L., K. R. Kunze, R. H. Hauge, and D. Hamill. 1977. Studies of matrix- isolated uranium tetrafluoride and its interactions with frozen gases. Journal of Physical Chemistry 81:1664. Mills, T. R. 1996. October 25, memo to Robert A. Penneman. NMT-6-DEM-96-033. Los Alamos National Laboratory. NRC (National Research Council). 1985. The Management of Radioactive Waste at the Oak Ridge National Laboratory: A Technical Review. Washington, D.C.: National Academy Press. NRC. 1995. An Assessment of Continued R&D into an Electrometallurgical Approach for Treating DOE Spent Nuclear Fuel. Washington, D.C.: National Academy Press. Nero, A. V., Jr. 1979. A Guidebook to Nuclear Reactors. Berkeley and Los Angeles, Calif.: University of California Press. ORNL (Oak Ridge National Laboratory). 1995. Hazard Screening: Molten Salt Reactor Experiment Facility. HS/7503/F/1/R1. Oak Ridge, Tenn. ORNL. 1996a. Molten Salt Reactor Experiment Remediation Project Reactive Gas Removal System Operations (Attachments A-D). Prepared by Lockheed Martin Energy Systems, Environmental Restoration Program, Oak Ridge, Tenn., December 16. ORNL. 1996b. Program Management Plan for the Molten Salt Reactor Experiment Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee. ORNL/ER-341. Prepared by Lockheed Martin Energy Systems, Environmental Restoration Program,. Oak Ridge, Tenn. Peretz, F. J. 1996a. Disposition of the Fluoride Fuel and Flush Salts from the Molten Salt Reactor Experiment at Oak Ridge National Laboratory. Presentation prepared by Lockheed Martin Energy Systems, Inc., at the American Institute for Chemical Engineering Spring Meeting, New Orleans, La., February. Peretz, F. J. 1996b. Disposition of the Fluoride Fuel and Flush Salts from the Molten Salt Reactor Experiment at Oak Ridge National Laboratory. Presentation to the National Research Council Buried and Tank Wastes Committee, prepared by Lockheed Martin Energy Systems, Inc., Oak Ridge, Tenn., May. Peretz, F. J. 1996c. Identification and Evaluation of Alternatives for the Disposition of Fluoride Fuel and Flush Salts from the Molten Salt Reactor Experiment at Oak Ridge National Laboratory, Oak Ridge, Tennessee. ORNL/ER-380. Oak Ridge, Tenn.: Oak Ridge National Laboratory. August. Pruvost, N. L., and H. C. Paxton. 1996. Nuclear Criticality Safety Guide. LA-12808. Los Alamos, N.Mex.: Los Alamos National Laboratory.

OCR for page 91
REFERENCES 91 Rushton, J., L. M. Toth, and F. Peretz. 1996a. Presentation to the National Research Council Panel on the Molten Salt Reactor Experiment, prepared by Lockheed Martin Energy Systems, Inc., Oak Ridge, Tenn., September 9. Rushton, J., L. M. Toth, F. Peretz. 1996b. Presentation to the National Research Council Panel on the Molten Salt Reactor Experiment, prepared by Lockheed Martin Energy Systems, Inc., Washington, D.C, October 8. Stratton, W. R., and D. R. Smith. 1989. A Review of Criticality Accidents, DOE/NCT-04. Washington, D.C.: U.S. Department of Energy. Thoma, R. E. 1971. Chemical Aspects of MSRE Operations. ORNL-4658. Oak Ridge, Tenn.: Oak Ridge National Laboratory. Trowbridge, L. D., S. H. Park, I. Remec, and J. P. Renier. 1995. Technical Bases of Selection of Trapping Technology for the MSRE Interim Vent and Trapping Project. K/TCD-1142. Oak Ridge, Tenn.: Oak Ridge K-25 Site. Weinberg, A. M. 1994. The First Nuclear Era: The Life and Times of a Technological Fixer. Woodbury, N.Y.: American Institute of Physics Press. Williams, D. F. 1995. Email memo to J. Rushton, and F. Peretz, copied to L. M. Toth and B. D. Patton, regarding gamma exposure, September 14. Williams, D. F., L. M. Toth, and G. D. Del Cull 1996. Chemical Interactions During Melting of the MSRE Fuel Salt. ORNL/M-5506. Oak Ridge, Tenn.: Oak Ridge National Laboratory. Zachariasen, W.H. 1948. Double fluorides of potassium or sodium with uranium, thorium, or lanthanum. Journal of the American Chemical Society 70:2147-2151. Senior Review Board Findings and Program Response Correspondence: · Correspondence to G. G. Fee from W. H. Hamilton, February 20, 1995: Report of the Senior Review Board, Molten Salt Reactor Experiment, Remediation of Uranium Mitigation Project. · Correspondence to Dr. B. D. Walker from L. E. Hall, February 24, 1995, transmitting Response to the Draft Report from the Senior Review Board Molten Salt Reactor Experiment (MSRE) Remediation Project. Correspondence to G. G. Fee from W. H. Hamilton, November 1, 1995: Report of Senior Review Board, Molten Salt Reactor Experiment, Remediation of Uranium Mitigation Project. Memorandum to Office of Environment, Safety and Health from G. S. Podonsky, December 4, 1995, transmitting Independent Oversight Special Review of the Molten Salt Reactor Experiment Oak Ridge National Laboratory. Memorandum to E. Cumesty from A. Lovell, December 11, 1995, transmitting memorandum of December 7 from W. Cooper to J. C. Hall, with attached EH Resident Surveillance Report Molten Salt Reactor Experiment at the Oak Ridge National Laboratory. Correspondence to W. H. Hamilton from J. E. Rushton, January 24, 1996: Molten Salt Reactor Experiment Senior Review Board.

OCR for page 92

Representative terms from entire chapter:

reactor experiment