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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.
J. H. Nadler, G. H. Miley, Y. Gu, T. Hochberg
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1639-1643
Plasma Engineering | doi.org/10.13182/FST92-A29955
Articles are hosted by Taylor and Francis Online.
There is considerable demand in the scientific community for a neutron generator with an output of 105–106 n/s that can be turned on or off, emits fusion neutrons, is self-calibrating, and can offer portable operation [1,2]. This paper will describe how an IEC-based neutron generator could satisfy these demands. Experimental data and modeling is presented for operation to the 105 n/s range. Direct extrapolation of the results indicate that with modest extension of operating parameters operation can be achieved in the 106–107 n/s range; with more aggressive modifications operation in the 108–10 n/s range can be possible.