This book discusses the technical alternatives for cleanup of radioactive fluoride salts that were the fuel for the Molten Salt Reactor Experiment, a novel nuclear reactor design that was tested in the 1960s at the Oak Ridge National Laboratory in Tennessee. These fluoride salts pose an unusual cleanup challenge. The book discusses alternatives for processing and removing the salts based on present knowledge of fluoride salt chemistry and nuclear reactions of the radioactive constituents.
National Research Council. 1997. Evaluation of the U.S. Department of Energy's Alternatives for the Removal and Disposition of Molten Salt Reactor Experiment Fluoride Salts. Washington, DC: The National Academies Press. https://doi.org/10.17226/5538.
|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|
|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|
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