Improved leach resistance of FLiBe by conversion to a substituted fluorapatite

Considerable work is focused on the development of molten salt fueled nuclear reactors. The treatment of the spent fuel in these systems has unique waste management issues. These typically halogen-based salts are known to be water soluble to various degrees. In addition to leachability issues, radio...

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Main Authors: Luis H. Ortega, Richard J. Livingston, Sean M. McDeavitt
Format: Article
Language:English
Published: Elsevier 2022-09-01
Series:Nuclear Materials and Energy
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179122001041
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author Luis H. Ortega
Richard J. Livingston
Sean M. McDeavitt
author_facet Luis H. Ortega
Richard J. Livingston
Sean M. McDeavitt
author_sort Luis H. Ortega
collection DOAJ
description Considerable work is focused on the development of molten salt fueled nuclear reactors. The treatment of the spent fuel in these systems has unique waste management issues. These typically halogen-based salts are known to be water soluble to various degrees. In addition to leachability issues, radiolysis may destabilize these salts when they are in solid form. FLiBe, a favored candidate for fluoride-salt-fueled reactor applications, presents significant waste management challenges. Conversion of FLiBe to fluorapatite may be an effective means to stabilize the salt for improved long-term stability and storage.
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spelling doaj.art-fa453dda46fe4395b49caaa3f07c70952022-12-22T04:05:00ZengElsevierNuclear Materials and Energy2352-17912022-09-0132101223Improved leach resistance of FLiBe by conversion to a substituted fluorapatiteLuis H. Ortega0Richard J. Livingston1Sean M. McDeavitt2Corresponding author.; Texas A&M University, Department of Nuclear Engineering, Fuel Cycle & Materials Laboratory, College Station, TX, United States of AmericaTexas A&M University, Department of Nuclear Engineering, Fuel Cycle & Materials Laboratory, College Station, TX, United States of AmericaTexas A&M University, Department of Nuclear Engineering, Fuel Cycle & Materials Laboratory, College Station, TX, United States of AmericaConsiderable work is focused on the development of molten salt fueled nuclear reactors. The treatment of the spent fuel in these systems has unique waste management issues. These typically halogen-based salts are known to be water soluble to various degrees. In addition to leachability issues, radiolysis may destabilize these salts when they are in solid form. FLiBe, a favored candidate for fluoride-salt-fueled reactor applications, presents significant waste management challenges. Conversion of FLiBe to fluorapatite may be an effective means to stabilize the salt for improved long-term stability and storage.http://www.sciencedirect.com/science/article/pii/S2352179122001041Molten salt reactorNuclear wasteSpent nuclear fuelFluorapatiteFLiBe
spellingShingle Luis H. Ortega
Richard J. Livingston
Sean M. McDeavitt
Improved leach resistance of FLiBe by conversion to a substituted fluorapatite
Nuclear Materials and Energy
Molten salt reactor
Nuclear waste
Spent nuclear fuel
Fluorapatite
FLiBe
title Improved leach resistance of FLiBe by conversion to a substituted fluorapatite
title_full Improved leach resistance of FLiBe by conversion to a substituted fluorapatite
title_fullStr Improved leach resistance of FLiBe by conversion to a substituted fluorapatite
title_full_unstemmed Improved leach resistance of FLiBe by conversion to a substituted fluorapatite
title_short Improved leach resistance of FLiBe by conversion to a substituted fluorapatite
title_sort improved leach resistance of flibe by conversion to a substituted fluorapatite
topic Molten salt reactor
Nuclear waste
Spent nuclear fuel
Fluorapatite
FLiBe
url http://www.sciencedirect.com/science/article/pii/S2352179122001041
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