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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.
S. Mori, H. Miura, S. Yamazaki, T. Suzuki, A. Shimizu, Y. Seki, T. Kunugi, S. Nishio, N. Fujisawa, A. Hishinuma, M. Kikuchi
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1744-1748
Magnetic Fusion Reactor and Systems Studies | doi.org/10.13182/FST92-A29973
Articles are hosted by Taylor and Francis Online.
This paper describes the preliminary design of the steady state tokamak reactor (SSTR) blanket cooled by a mixture of helium gas and fine solid particles. Light yet highly heat resistant material, titanium aluminide (TiAl), is used as structural material. Thickness of tritium breeding blanket using lithiated ceramics and beryllium neutron multiplier is minimized and high-temperature and non-breeding shield blanket is installed to enhance blanket energy multiplication. It is found that TiAl is advantageous in radioactive waste management because the contact dose rate of TiAl first wall attenuates rapidly. The gas-particulate mixture coolant lowers the helium pressure to 5 MPa and reduces the volumetric flow rate when compared to a pure helium-cooled blanket. The net thermal efficiency larger than 40 % can be achieved with the outlet coolant temperature of 700°C.