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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.
Koichi Maki
Fusion Science and Technology | Volume 8 | Number 3 | November 1985 | Pages 2655-2664
Technical Paper | Blanket Engineering | doi.org/10.13182/FST85-A24687
Articles are hosted by Taylor and Francis Online.
A fusion reactor blanket having a large tritium breeding ratio (TBR) is proposed. The blanket has a front breeder zone on the plasma side near its multiplier. A suitable zone thickness is 1 cm when 6Li enrichment is 50%. Combined with a multiplier composed of only ∼18-cm-thick beryllium, the TBR is maximized at a value over 20% larger than that of a blanket without a front breeder zone. Since the beryllium multiplier is supposed to include 5% of SUS as structural material in addition to cooling channels, a 12-cm-thick multiplier gives the maximum TBR as >1.4 for the blanket with the front breeder zone.