My Account Log in

3 options

Evaluation of the U.S. Department of Energy's alternatives for the removal and disposition of molten salt reactor experiment fluoride salts / Molten Salt Panel of the Committee on Remediation of Buried and Tank Wastes, Board on Radioactive Waste Management, Commission of Geosciences, Environment, and Resources, National Research Council.

EBSCOhost Academic eBook Collection (North America) Available online

View online

Ebook Central Academic Complete Available online

View online

National Academies Press Available online

View online
Format:
Book
Contributor:
National Research Council (U.S.). Committee on Remediation of Buried and Tank Wastes. Molten Salt Panel.
Language:
English
Subjects (All):
Radioactive waste disposal--United States.
Radioactive waste disposal.
Molten salt reactors.
Fluorides.
Physical Description:
1 online resource (147 p.)
Edition:
1st ed.
Other Title:
Alternatives for the removal and disposition of molten salt reactor experiment fluoride salts
Place of Publication:
Washington, D.C. : National Academy Press, 1997.
Language Note:
English
Summary:
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.
Contents:
Evaluation of the U.S. Department of Energy's
Copyright
Acknowledgments
Preface
Contents
Executive Summary
THE MSRE FACILITY AND CURRENT REMEDIATION PLANS
PURPOSE OF THIS REPORT
SUMMARY OF FINDINGS ON THREE MAJOR ISSUES
MAJOR CONCLUSIONS
MAJOR RECOMMENDATIONS
1-Introduction
CURRENT STATUS OF THE MSRE
ROLE OF THE NATIONAL RESEARCH COUNCIL
SCOPE AND ORGANIZATION OF THIS REPORT
2-Radiolysis and Nuclear Reactions
RADIOACTIVE SOURCE TERMS
RADIATION EFFECTS AND GENERAL COMMENTS
Radiation-Induced Liberation of Fluorine and Uranium Hexafluoride Gases
Radiation Decomposition of Solid Uranium Hexafluoride
Long-Term Effects of Leaving Plutonium in the Salt After Uranium Removal
EXCESS OF REDUCING SPECIES IN THE SALT AND HAZARDS OF SIMPLE REMELTING
3-Fluoride Salt Chemistry, Partitioning, and System Corrosion
CHEMISTRY RELEVANT TO THE PRESENT STATUS
Chemical Consequences of Radiolysis
PARTITIONING OF URANIUM FROM THE SALT
PLUTONIUM PARTITIONING BY FLUORINATION
NONFLUORINATION OPTION FOR PLUTONIUM SEPARATION
SYSTEM CORROSION ISSUES
Radiation-Induced Corrosion Questions
4-Preferred Technical Approach
COMMENTS ON PROCESS STEPS
DEVELOPMENT OF A PREFERRED APPROACH
5-Comments on Specific Separation Technologies
FLUORINATION
Direct Fluorination
Hydrofluorination
Alternative Fluorinating Agents
ELECTROREFINING
DISTILLATION OF MOLTEN SALT
AQUEOUS DISSOLUTION AND SEPARATION
Criticality Concerns in Aqueous Processing
Fluoride Removal
Conclusions on Aqueous Processing
STABILIZATION TECHNOLOGIES
6-Nuclear Criticality Considerations
CRITICALITY ISSUES IN PROCESSING
CRITICALITY HAZARD OF REMELTING THE FLUORIDE SALTS IN THE DRAIN TANKS
RATIONALE FOR TECHNICAL INSIGNIFICANCE OF A CRITICALITY EXCURSION
CONCLUDING COMMENTS.
7-Strategic Alternatives
PERMANENT DISPOSAL IN THE DRAIN TANKS
DISPOSAL OF ALL KEY CONTAMINANTS IN THE FEDERAL REPOSITORY
DISPOSAL OF KEY CONTAMINANTS IN THE SALT RESIDUE IN THE WASTE ISOLATION PILOT PLANT (WIPP)
DISPOSAL OF KEY CONTAMINANTS IN SALT RESIDUE IN THE FEDERAL REPOSITORY
REUSE OF THE SALT
INTERIM STORAGE
RATIONALE FOR REJECTING THE FIRST SIX ALTERNATIVES
INTERIM VERSUS PERMANENT STORAGE AND DISPOSAL
8-Management of MSRE Hazards
CURRENT HAZARDS
HAZARD MANAGEMENT ACTIVITIES
CRUCIAL ROLE OF FURTHER ACTIVITIES FOR CONDITION AND PROCESS ASSESSMENT
MAJOR RECOMMENDATION CONCERNING HAZARDS
DETAILED RECOMMENDATIONS REGARDING HAZARDS
9-Summary and Responses to Questions in Statement of Task
TECHNICAL SUMMARY
STRATEGY FOR REMEDIATION
Where Is the Uranium?
How Can a Condition Assessment Affect Remediation Plans?
The Panel's Preferred Alternative
Hazards
RESPONSES TO QUESTIONS IN STATEMENT OF TASK
Question 1
Question 2
The Consequences of Failure to Complete According to Plan
Cost Estimates
A Possible Strategy
Question 3
PANEL PERSPECTIVE
OVERALL CONCLUSION
References
Appendixes
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
Consultants.
Notes:
Bibliographic Level Mode of Issuance: Monograph
Includes bibliographical references.
ISBN:
9786610191765
9780309174923
0309174929
9781280191763
1280191767
9780309590105
0309590108
9780585085395
0585085390
OCLC:
614743023

The Penn Libraries is committed to describing library materials using current, accurate, and responsible language. If you discover outdated or inaccurate language, please fill out this feedback form to report it and suggest alternative language.

Find

Home Release notes

My Account

Shelf Request an item Bookmarks Fines and fees Settings

Guides

Using the Find catalog Using Articles+ Using your account