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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.
Y. S. Horowitz, M. Moscovitch, J. M. Mack, H. Hsu, E. Kearsley
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 233-240
Technical Paper | doi.org/10.13182/NSE86-A17266
Articles are hosted by Taylor and Francis Online.
Electron Monte Carlo calculations using CYLTRAN and a new PHSECE (Photon-Produced Secondary Electrons) technique were carried out to estimate electron fluences and energy deposition profiles near LiF/Al and LiF/Pb material interfaces undergoing 60Co gamma irradiation. Several interesting and new features emerge: (a) although the buildup of the secondary electron fluences at the interfaces of the irradiated media is approximately exponential, the value of the electron mass fluence buildup coefficient, γ, is not equal to the electron mass fluence attenuation coefficient, β;(b) the β value of the attenuation of the gamma generated electron fluences at the cavity/medium interfaces is strongly dependent on the Z of the adjacent material; and (c) for LiF/Pb there is a significant “intrusion” energy deposition mode arising from sidescattering in the wall material (lead). These new features of interface dosimetry (at least items a and b) are incorporated into the photon general cavity expressions of Burlin (as modified by Horowitz, Dubi, and Moscovitch) and Kearsley and compared with experimental data.