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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.
Y. Oyama, S. Yamaguchi, K. Tusda, Y. Ikeda, C. Konno, H. Maekawa, T. Nakamura, K. G. Porges, E. F. Bennett, R. F. Mattas
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1293-1298
Blanket Nucleonics Experiment | doi.org/10.13182/FST89-A39868
Articles are hosted by Taylor and Francis Online.
As a part of the Phase-II experimental series of JAERI/USDOE collaborative program on fusion blanket neutronics, the phase-IIB experiment has been performed. The experiment provides information of neutron multiplication and reflection by the inner berryllium layer in a full-coverage blanket geometry. The measurements were carried out at the positions in the test zone on tritium production rate (TPR) using various methods, on reaction rate using foil activation technique and on neutron energy spectrum using NE213 and gas proportional counters. The experimental results showed that the effect of the full-coverage beryllium was a 10% increase for T7 (TPR for 7Li) and a factor of 2–5 increase for T6 (TPR for 6Li). The increase of the integrated TPR for natural lithium (Tn) in the test zone due to the inner beryllium layer was above 60% compared to the non-beryllium system in the Phase-II geometry.