Evaluation of the U.S. Department of Energy's alternatives for the removal and disposition of molten salt reactor experiment fluoride salts
Author(s)
Bibliographic Information
Evaluation of the U.S. Department of Energy's alternatives for the removal and disposition of molten salt reactor experiment fluoride salts
National Academy Press, 1997
- Other Title
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Alternatives for the removal and disposition of molten salt reactor experiment fluoride salts
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Note
Includes bibliographical references
Description and Table of Contents
Description
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.
Table of Contents
Front Matter
Executive Summary
1 Introduction
2 Radiolysis and Nuclear Reactions
3 Fluoride Salt Chemistry, Partitioning, and System Corrosion
4 Preferred Technical Approach
5 Comments on Specific Separation Technologies
6 Nuclear Criticality Considerations
7 Strategic Alternatives
8 Management of MSRE Hazards
9 Summary and Responses to Questions in Statement of Task
References
Appendix A: List of Materials Reviewed
Appendix B: Alternative Fluorinating Agents
Appendix C: Contamination Concerns Relating to Radon Gas Spread
Appendix D: Use of a Nuclear Poison to Inhibit Nuclear Criticality
Appendix E: Hazard Scoping of Major Actions for Remediation
Appendix F: List of Acronyms and Abbreviations
Appendix G: Glossary
Appendix H: Biographical Sketches of Molten Salt Panel Members and
Consultants
Table of Contents
- 1 Front Matter
- 2 Executive Summary
- 3 1 Introduction
- 4 2 Radiolysis and Nuclear Reactions
- 5 3 Fluoride Salt Chemistry, Partitioning, and System Corrosion
- 6 4 Preferred Technical Approach
- 7 5 Comments on Specific Separation Technologies
- 8 6 Nuclear Criticality Considerations
- 9 7 Strategic Alternatives
- 10 8 Management of MSRE Hazards
- 11 9 Summary and Responses to Questions in Statement of Task
- 12 References
- 13 Appendix A: List of Materials Reviewed
- 14 Appendix B: Alternative Fluorinating Agents
- 15 Appendix C: Contamination Concerns Relating to Radon Gas Spread
- 16 Appendix D: Use of a Nuclear Poison to Inhibit Nuclear Criticality
- 17 Appendix E: Hazard Scoping of Major Actions for Remediation
- 18 Appendix F: List of Acronyms and Abbreviations
- 19 Appendix G: Glossary
- 20 Appendix H: Biographical Sketches of Molten Salt Panel Members and Consultants
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