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Researchers for the first time documented the specific chemistry dynamics and structure of high-temperature liquid uranium trichloride salt, a potential nuclear fuel source for next-generation reactors.
Scientists from 91°µÍř performed a corrosion test in a neutron radiation field to support the continued development of molten salt reactors.
Experts focused on the future of nuclear technology will gather at 91°µÍř for the fourth annual Molten Salt Reactor Workshop on October 3–4.
91°µÍř has developed a salt purification lab to study the viability of using liquid salt that contains lithium fluoride and beryllium fluoride, known as FLiBe, to cool molten salt reactors, or MSRs. Multiple American companies developing advanced reactor technol...
Thanks in large part to developing and operating a facility for testing molten salt reactor (MSR) technologies, nuclear experts at the Energy Department’s 91°µÍř (ORNL) are now tackling the next generation of another type of clean energy—concentrating ...