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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.
D. W. Kneff, B. M. Oliver., Harry Farrar IV, L. R. Greenwood
Nuclear Science and Engineering | Volume 92 | Number 4 | April 1986 | Pages 491-524
Technical Paper | doi.org/10.13182/NSE86-A18608
Articles are hosted by Taylor and Francis Online.
The results of an extensive series of total helium production cross-section measurements for incident neutrons in the 14- to 15-MeV energy region are presented, and an experimental data base for the prediction of helium generation in candidate fusion reactor materials is provided. The measurements were made by isotope-dilution gas mass spectrometry. They include the pure elements Be, B, C, O, F, AI, Si, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Y, Zr, Nb, Mo, Ag, Sn, Ta, Pt, Au, and Pb; the separated isotopes of B, Fe, Ni, Cu, and Mo; and the alloy steels Type 316 stainless steel, HT-9, and 9 Cr-1 Mo. The results are in generally good agreement with other total helium production measurements in the literature, but comparisons with the ENDF/B- V nuclear data file indicate that the helium gas production files require revision for the structural elements vanadium, chromium, manganese, cobalt, and nickel. Comparisons with published cross sections for individual reaction channels indicate that reactions other than (n,α) contribute significantly to helium production in several materials.