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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.
Hiroshi Maekawa, Yukio Oyama, Tomoo Suzuki, Yujiro Ikeda, Tomoo Nakamura
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1165-1170
Neutronics and Shielding | doi.org/10.13182/FST83-A23016
Articles are hosted by Taylor and Francis Online.
Angle-dependent neutron leakage spectra above 0.5 MeV from Li2O slab assemblies were measured accurately by the time-of-flight method. The measured angles were 0°, 12.2°, 24.9°, 41.8° and 66.8°. The sizes of Li2O assemblies were 31.4 em in equivalent radius and 5.06, 20.24 and 40.48 em in thickness. The data were analyzed by a new transport code “BERMUDA-2DN”. Time-independent transport equation is solved for two-dimensional, cylindrical, multi-regional geometry using the direct integration method in a multi-group model. The group transfer kernels are accurately obtained from the double-differential cross section data without using Legendre expansion. The results were compared absolutely. While there exist discrepancies partially, the calculational spectra agree well with the experimental ones as a whole. The BERMUDA code was demonstrated to be useful for the analyses of the fusion neutronics and shielding.