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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.
H. Hasegawa, H. Nakashima, T. Matsui, M. Ohta
Nuclear Science and Engineering | Volume 86 | Number 4 | April 1984 | Pages 405-409
Technical Note | doi.org/10.13182/NSE84-A18642
Articles are hosted by Taylor and Francis Online.
An examination is made of the helical geometry effect on the tritium breeding in the Heliotron reactor blanket. Calculations are performed with the three-dimensional Monte Carlo code MORSE-I for the cylindrical, torus and helical geometry models, each approximating the configuration of the Heliotron reactor in various degrees. A comparison of the tritium breeding ratios obtained between these models indicates that the helical geometry effects would be modest. However, it is found that there exists neutron streaming through between blanket regions, due to the helical geometry of the system.