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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.
Bastiaan J. Braams, Clifford E. Singer
Fusion Science and Technology | Volume 9 | Number 2 | March 1986 | Pages 320-327
Technical Paper | Plasma Engineering | doi.org/10.13182/FST86-A24718
Articles are hosted by Taylor and Francis Online.
Analytic and two-dimensional computational solutions for the plasma parameters near a toroidally symmetric limiter are illustrated for the projected parameters of a Tokamak Fusion Core Experiment (TFCX). The temperature near the limiter plate is below 20 eV, except when the density 10 cm inside the limiter contact is 8 × 1013 cm−3 or less and the thermal diffusivity in the edge region is 2 × 104 cm2/s or less. Extrapolation of recent experimental data suggests that neither of these conditions is likely to be met near ignition in TFCX, so a low plasma temperature near the limiter should be considered a likely possibility.