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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.
Asashi Kitaioto, Mitsuhiro Ohta
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 971-976
Material; Storage and Processing | doi.org/10.13182/FST92-A29877
Articles are hosted by Taylor and Francis Online.
The separation performance of tritium by the thermal diffusion method with low inventory was simulated as an alternative method to the cryogenic distillation in Fusion Fuel Cycle. The separation performance of thermal diffusion method was evaluated by the ternary transport equations with isotope exchange reaction. The results for HT - H2 system, show the isotope exchange reaction, H2 + T2 = 2HT, plays an important role in the separation performance of tritium, even in a tracer level of tritium.
