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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.
A. Tsechanski, G. Shani
Nuclear Science and Engineering | Volume 87 | Number 2 | June 1984 | Pages 189-194
Technical Note | doi.org/10.13182/NSE84-A17711
Articles are hosted by Taylor and Francis Online.
A simple method for the measurement of the loss of deuteron energy in a solid Ti-T target of a neutron generator is described. The method is based on a comparison of the results of measurements of the full-width at half-maximum of the peak in the spectrum of a collimated T(d,n)4He neutron beam directed at nominal angles of O and 95 deg to the neutron generator axis. The average deuteron energy loss in the solid Ti-T target is estimated to be (58.5 ± 4.0) keV at 150-kV nominal accelerating voltage of the neutron generator. The neutron spectrum measurements were carried out by a 2- × 2-in. NE-213 liquid scintillator. The proton recoil spectra created in the liquid scintillator were unfolded into the neutron energy spectra with the FORIST unfolding code.