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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.
Malte Edenius, Ake Ahlin
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 342-351
Technical Paper | doi.org/10.13182/NSE88-A29048
Articles are hosted by Taylor and Francis Online.
The CASMO code is an assembly spectrum code that uses multigroup integral transport theory with four thermal energy groups for the two-dimensional calculation. The latest version, CASMO-3, contains several new features, specifically a new data library, multibundle capability, gamma detector calculation, flux discontinuity factor edit, and an option for generating transport theory corrected baffle/reflector data. Extensive benchmarking, including comparisons against cold- and high-temperature critical experiments, Monte Carlo calculations, measured isotopics, and power reactor core follow, has verified that accurate results are obtained. The new multibundle capability has been used for studies of interassembly spectrum coupling and for validation of core physics methods.