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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. Voignier, S. Joly, G. Grenier
Nuclear Science and Engineering | Volume 93 | Number 1 | May 1986 | Pages 43-56
Technical Paper | doi.org/10.13182/NSE83-A17415
Articles are hosted by Taylor and Francis Online.
Absolute neutron capture cross sections for natural elements of copper, yttrium, zirconium, niobium, lanthanum, gadolinium, terbium, tantalum, tungsten, rhenium, platinum, thallium, bismuth, and separated isotopes of 63Cu, 65Cu, 155Gd, 156Gd, 157Gd, 158Gd, 160Gd, 182W, 183W, 184W, 186W, 203Tl, 205Tl have been measured in the 0.5- to 3.0-MeV energy range. For most of these nuclides and isotopes, available data were scarce and discrepant, especially for neutron energies above 0.7 MeV. A spectrum-fitting method was developed to deduce the radiative capture cross section from prompt gamma rays emitted by the sample. The gamma rays were recorded by a NaI scintillator surrounded by an annular detector and the capture gamma-ray spectrum was obtained by unfolding the observed pulse-height distribution with the response function of the detector. Gamma-ray spectra emitted in the capture of 0.5-MeV neutrons as well as the multiplicity of the gamma-ray transitions are presented.