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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 12 | Number 2 | September 1987 | Pages 310-319
Blanket Engineering | doi.org/10.13182/FST87-A11963788
Articles are hosted by Taylor and Francis Online.
When a blanket concept is applied to the actual reactor design, various structural changes such as material thickness, material volume fractions, etc., are made to adjust the overall design to meet lifetime and material stress requirements. After these changes, the new tritium breeding ratio (TBR) is required to be easily and quickly estimated. Hence, an analytical TBR formula was derived by separating absorption, scattering, neutron multiplication, and tritium production cross sections at high energies above the multiplication reaction threshold from those at low energies near the thermal energy. The formula was applied to three blanket types. The TBR values calculated by this formula agreed with those of an ANISN transport code within 5%.