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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.
B. Navinsek
Fusion Science and Technology | Volume 6 | Number 2 | September 1984 | Pages 491-498
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-A23226
Articles are hosted by Taylor and Francis Online.
Some candidate fusion materials such as nickel-base alloys and graphites were studied, because of their importance as first wall components in CTR devices. Polycrystalline samples of Inconel 600, Inconel 625, Nimonic alloy PE 16, nuclear grade graphite ATJ and pyrolytic graphite were investigated. Results for surface damage and topography, blistering, flaking, ion erosion and sputtering yields are reported for irradiations with low energy He+ ions (5–12 keV) at room temperature, using total ion doses up to 2×1019 ions cm−2. SEM, TEM and AES analyses were used to identify surface damage, structure and compositional changes after irradiation. Comparative studies of the ion erosion yield of nickel-base alloys, as measured by the step-height technique, were made. Total sputtering yields were determined dynamically for sputtered films of these alloys using a quartz crystal microbalance. The yields were studied as a function of ion dose, energy and surface roughness.