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Beryllium Interactions in Molten Salts.

DE2008911182

Publication Date	2006
Personal Author	Simpson, M. F.; Smolik, G. S.; Pinhero, P. J.; Tanaka, S.; Petti, D. A.
Page Count	6
Abstract	Molten flibe (2LiFDTBeF2) is a candidate as a cooling and tritium breeding media for future fusion power plants. Neutron interactions with the salt will produce tritium and release excess free fluorine ions. Beryllium metal has been demonstrated as an effective redox control agent to prevent free fluorine, or HF species, from reacting with structural metal components. The extent and rate of beryllium solubility in a pot design experiments to suppress continuously supplied hydrogen fluoride gas has been measured and modeled. This paper presents evidence of beryllium loss from specimens, a dependence of the loss upon bi-metal coupling, i.e., galvanic effect, and the partitioning of the beryllium to the salt and container materials. Various posttest investigative methods, viz., scanning electron microscopy (SEM), Auger electron spectroscopy (AES) and x-ray photoelectron spectroscopy (XPS) were used to explore this behavior.
Keywords	Beryllium Molten salts Auger electron spectroscopy Breeding Containers Design Flibe Fluorine Fluorine ions Hydrofluoric acid Neutrons Power plants Scanning electron microscopy Solubility Thermonuclear reactor materials Tritium X-ray spectroscopy
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Engineering Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200819
Contract Number	DE-AC07-99ID-13727

Beryllium Interactions in Molten Salts.

Beryllium Interactions in Molten Salts.
DE2008911182

Publication Date	2006
Personal Author	Simpson, M. F.; Smolik, G. S.; Pinhero, P. J.; Tanaka, S.; Petti, D. A.
Page Count	6
Abstract	Molten flibe (2LiFDTBeF2) is a candidate as a cooling and tritium breeding media for future fusion power plants. Neutron interactions with the salt will produce tritium and release excess free fluorine ions. Beryllium metal has been demonstrated as an effective redox control agent to prevent free fluorine, or HF species, from reacting with structural metal components. The extent and rate of beryllium solubility in a pot design experiments to suppress continuously supplied hydrogen fluoride gas has been measured and modeled. This paper presents evidence of beryllium loss from specimens, a dependence of the loss upon bi-metal coupling, i.e., galvanic effect, and the partitioning of the beryllium to the salt and container materials. Various posttest investigative methods, viz., scanning electron microscopy (SEM), Auger electron spectroscopy (AES) and x-ray photoelectron spectroscopy (XPS) were used to explore this behavior.
Keywords	Beryllium Molten salts Auger electron spectroscopy Breeding Containers Design Flibe Fluorine Fluorine ions Hydrofluoric acid Neutrons Power plants Scanning electron microscopy Solubility Thermonuclear reactor materials Tritium X-ray spectroscopy
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Engineering Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200819
Contract Number	DE-AC07-99ID-13727