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Scientists have tested a novel heat-shielding graphite foam, originally created at Oak Ridge National Laboratory, at Germany’s Wendelstein 7-X stellarator with promising results for use in plasma-facing components of fusion reactors.
Oak Ridge National Laboratory scientists analyzed more than 50 years of data showing puzzlingly inconsistent trends about corrosion of structural alloys in molten salts and found one factor mattered most—salt purity.
Scientists from Oak Ridge National Laboratory 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 Oak Ridge National Laboratory for the fourth annual Molten Salt Reactor Workshop on October 3–4.