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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.
A. C. Merchant, P. E. Hodgson, H. R. Schelin
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 132-144
Technical Paper | doi.org/10.13182/NSE92-A23929
Articles are hosted by Taylor and Francis Online.
The experimental data on the interactions of I- to 20-MeV neutrons with 238U are summarized, together with the theoretical analyses. Particular attention is devoted to the elastic and inelastic scattering cross sections because of their practical importance. Functional forms for the surface and volume imaginary terms of the optical potential are chosen so that the dispersion relation, by means of which these terms generate additional contributions to the real part of the optical potential, can be evaluated analytically. The fission and capture cross sections are not included as they have been extensively reviewed elsewhere.