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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.
R. G. Alsmiller, Jr., R. T. Santoro, J. F. Manneschmidt, J. M. Barnes
Fusion Science and Technology | Volume 7 | Number 2 | March 1985 | Pages 197-200
Technical Note | Plasma Engineering | doi.org/10.13182/FST85-A24534
Articles are hosted by Taylor and Francis Online.
The ion temperature of a deuterium plasma with a Maxwellian distribution can be determined by measuring the transmission of the deuterium-deuterium (D-D) neutrons, i.e., neutrons produced by the reaction D + D → n + 3He, through liquid oxygen. In practice the measurement requires both collimation and shielding to ensure that the attenuation of only those neutrons emitted directly from the plasma is measured. Calculated results are presented of the collimation and shielding required to reduce the background so that the ion temperature can be measured. The geometric configuration used in the calculations is that of the Impurity Studies Experiment (ISX) at the Oak Ridge National Laboratory, but the results will provide insight into the application of the measurement method at other plasma facilities. Results are presented for D-D plasma temperatures of 2, 6, and 10 keV and for two sizes of NE-213 detectors. It is concluded that the counting rates are too low to make the measurement feasible at ISX.