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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.
Arthur W. Dalton
Fusion Science and Technology | Volume 12 | Number 3 | November 1987 | Pages 409-415
Technical Paper | Tritium System | doi.org/10.13182/FST87-A25072
Articles are hosted by Taylor and Francis Online.
A cylinder of natural lithium carbonate, supported on a slab of graphite, was irradiated from above by a low-intensity source of 14-MeV neutrons and the tritium produced within it subsequently determined from measurements of beta activity. Results obtained for small lithium carbonate detectors highly enriched in 6Li (96%) or 7Li (99.9%) at six positions along the cylinder axis were compared with predictions based on three-dimensional Monte Carlo calculations and multi-group cross-section data. The experimental accuracy was sufficient to detect deviations from theory > 7% with a 95% level of confidence. On this basis, good agreement with theoretical predictions was obtained for the 7Li results. For the 6Li data, however, significant differences were observed in the lower half of the assembly. A detailed analysis indicated that these deviations could not be explained in terms of conceivable environmental perturbations of the neutron flux and may arise as a consequence of inadequate representation of anisotropic neutron scattering.