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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. Ferenc, B. Antolković, G. Paić, M. Zadro, S. Blagus
Nuclear Science and Engineering | Volume 101 | Number 1 | January 1989 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE89-A23590
Articles are hosted by Taylor and Francis Online.
A metallic 9Be target was bombarded with 14.6-MeV neutrons. Double-differential cross sections were measured for the (n, α) reaction in the angular range from 0 to 100 deg. The measured alpha-particle spectra and complementary neutron spectra from the literature were analyzed in terms of a combination of sequential and simultaneous breakups. The results show that ∼50% of the total inelastic cross section is due to simultaneous breakup n + 9Be → n + α + 5He, while the remainder is mainly due to neutron inelastic scattering to the three excited states of 9Be: 2.43, 6.76, and 11.28 MeV. This analysis gives evidence of the validity of the constant matrix element model and contradicts evaluations that ignore the simultaneous breakup contributions.