Tritium Content and Chemical Form in Nuclear Graphite from Molten Fluoride Salt Irradiations
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DOI: 10.1080/15361055.2020.1712993
Abstract: Abstract Advanced reactor applications that use a molten fluoride salt coolant and graphite moderator are under consideration as next-generation energy technologies. For molten salts with lithium or beryllium, such as flibe (2LiF-BeF2), the production of… read more here.
Keywords: molten fluoride; tritium; form; content chemical ... See more keywords