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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.
H. Märten, D. Richter, D. Seeliger, W. D. Fromm, R. Böttger, H. Klein
Nuclear Science and Engineering | Volume 106 | Number 3 | November 1990 | Pages 353-366
Technical Paper | doi.org/10.13182/NSE90-A29063
Articles are hosted by Taylor and Francis Online.
The 252Cf neutron spectrum is measured at high energies with a miniature ionization chamber and two different NE-213 neutron detectors. The gamma-ray background and the main cosmic background caused by muons were suppressed by applying efficient pulse-shape discrimination. On the basis of two-dimensional spectroscopy of the neutron time-of-flight and scintillation pulse height, the sliding bias method is used to minimize experimental uncertainties. The experimental data, corrected for several systematic influences, confirm earlier results that show negative deviations from a reference Maxwellian distribution with a 1.42-MeV spectrum “temperature” for neutron energies above 6 MeV. Experimental results of this work are compared with various statistical model approaches to the 252Cf(sf) neutron spectrum.