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May 31–June 3, 2026
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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.
Kiyoshi Takeuchi, Shun-ichi Tanaka
Nuclear Science and Engineering | Volume 90 | Number 2 | June 1985 | Pages 158-164
Technical Paper | doi.org/10.13182/NSE85-A17673
Articles are hosted by Taylor and Francis Online.
Gamma-ray exposure buildup factors are calculated using a discrete ordinates direct integration code, PALLAS-PL, SP-Br, for water, concrete, iron, and lead for point isotropic sources. These data include the effects of secondary photon sources arising from Compton scattering, bremsstrahlung, and annihilation. Comparisons of these results without bremsstrahlung to values obtained earlier by moments calculations show reasonable agreement, except in some instances of deep penetration. The calculated buildup factors are tabulated for incident energies of 0.1 to 15 MeV (except for lead, where the lower energy is 0.4 MeV) and for penetration depths as great as 40 mfp.