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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.
L. P. Ku, H. W. Hendel, S. L. Liew, J. D. Strachan
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 418-430
Technical Paper | Experimental Device | doi.org/10.13182/FST91-A29382
Articles are hosted by Taylor and Francis Online.
Accurate determinations of fusion neutron yields on the Tokamak Fusion Test Reactor (TFTR) require that the neutron detectors be absolutely calibrated in situ, using neutron sources of known strengths. For such calibrations, numerical simulations of neutron transport can be powerful tools in the design of experiments and the study of measurement results. On the TFTR, numerical calibration experiments are frequently used to complement actual detector calibrations. Calculational approaches and transport models used in these numerical simulations are presented and the results from a simulation of the calibration of 235U fission detectors carried out in December 1988 are summarized.