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Batch-Scale Hydrofluorination of Li27BeF4 to Support Molten Salt Reactor Development
Author(s) -
Brian Kelleher,
Kieran Dolan,
Paul Brooks,
Mark Anderson,
Kumar Sridharan
Publication year - 2015
Publication title -
journal of nuclear engineering and radiation science
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.278
H-Index - 10
eISSN - 2332-8983
pISSN - 2332-8975
DOI - 10.1115/1.4030963
Subject(s) - oak ridge national laboratory , coolant , molten salt , corrosion , nuclear engineering , materials science , blanket , molten salt reactor , radioactive waste , waste management , radiochemistry , nuclear chemistry , metallurgy , chemistry , nuclear physics , composite material , physics , engineering
Li 2 BeF 4 , or flibe, is the primary candidate coolant for the fluoride-salt-cooled high-temperature nuclear reactor (FHR). Kilogram quantities of pure flibe are required for repeatable corrosion tests of modern reactor materials. This paper details fluoride salt purification by the hydrofluorination–hydrogen process, which was used to regenerate 57.4 kg of flibe originating from the secondary loop of the molten salt reactor experiment (MSRE) at Oak Ridge National Laboratory (ORNL). Additionally, it expounds upon necessary handling precautions required to produce high-quality flibe and includes technological advancements which ease the purification and analysis process. Flibe batches produced at the University of Wisconsin are the largest since the MSRE program, enabling new corrosion, radiation, and thermal hydraulic testing around the United States.

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