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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Latest News
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.
A. S. DiGiovine, J. P. Gorski, M. A. Tremblay
Nuclear Science and Engineering | Volume 103 | Number 4 | December 1989 | Pages 420-426
Technical Note | doi.org/10.13182/NSE89-A23694
Articles are hosted by Taylor and Francis Online.
The advanced nodal code SIMULA TE-3 includes the capability to generate detailed pin-by-pin power distributions. Yankee Atomic Electric Company has performed an extensive series of benchmark calculations verifying the accuracy of this capability. Fuel depletion and fuel depletion after shuffling applications were examined. Comparisons were made among SIMULATE-3, higher order transport theory calculations, and calculations performed using fine-mesh finite difference diffusion theory. Detailed pin power data from multiassembly (colorsets) and quarter-core geometries were compared. The results demonstrate the accuracy of SIMULA TE-3 relative to currently accepted methods of generating pin power data.