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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.
Y. Gotoh
Fusion Science and Technology | Volume 6 | Number 2 | September 1984 | Pages 424-427
Technical Paper | Selected papers from the Ninth International Vacuum Congress and the Fifth International Conference on Solid Surfaces (Madrid, Spain, September 26-October 1, 1983) | doi.org/10.13182/FST84-A23217
Articles are hosted by Taylor and Francis Online.
Trapping and release of deuterium at a pyrolytic graphite basal face are studied by using X-ray photoelectron spectroscopy. The trapped deuterium density in nearly 10 atomic layers of the surface is estimated through measurement of C 1s positive shift due to C-D bond formation. Most of the deuterium atoms trapped in the graphite to saturation at room temperature are not released by the heat-treatment at up to 450°C. The trapped-deuterium density is found to reach a lower equilibrium value by the bombardment to saturation at above 180°C than those by the bombardment at below 180°C. The equilibrium trapped-deuterium density decreases down to one third, as the target temperature is raised above 180°C to 430°C. The decrease in the equilibrium trapped-deuterium density at above 180°C is explained by the ion-induced re-emission of the deuterium.