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Latest News
INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
Kan Ashida, Masao Matsuyama, Kuniaki Watanabe
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 735-740
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25222
Articles are hosted by Taylor and Francis Online.
Graphite is the primary candidate for the first wall of magnetically confined fusion devices. For this application, it is important to know the surface properties and trap/release behavior of hydrogen isotopes to understand fuel recycling/inventory in the graphite first wall. The surface analysis of as-received graphite revealed that the inherent hydrogen content is larger in isotropic compared to the anisotropic graphite. This is due to the presence of non-graphitized carbon atoms in the isotropic graphite which act as the trapping sites of hydrogen atoms. Ion bombardment causes the reduction of the crystallite size of graphite (damage modification), leading to amorphous-like structure. The thermal desorption spectra of hydrogen isotopes consisted of three desorption peaks for the modified graphite. The desorption mechanisms and parameters of three peaks are determined. These parameters were used to estimate the fuel inventory in the graphite.