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May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
B. Rouben, K. S. Brunner, D. A. Jenkins
Nuclear Science and Engineering | Volume 98 | Number 2 | February 1988 | Pages 139-148
Technical Paper | doi.org/10.13182/NSE88-A28493
Articles are hosted by Taylor and Francis Online.
A refinement is proposed to the current method of evaluating lattice properties for use in calculations of Canada deuterium uranium flux distributions. This refinement, labeled the local-parameter calculation, takes into account locally appropriate values of coolant density, fuel temperature, and flux/power level where core average values were previously used. The local-parameter calculation has been implemented and tested. Results are compared to those of previous calculations and of independent methods based on in-core measurements.
