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May 31–June 3, 2026
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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.
C. Coceva, P. Giacobbe, M. Magnani
Nuclear Science and Engineering | Volume 91 | Number 2 | October 1985 | Pages 209-219
Technical Paper | doi.org/10.13182/NSE85-A27442
Articles are hosted by Taylor and Francis Online.
The analysis of two 91Zr neutron transmission experiments performed some years ago at the Oak Ridge National Laboratory and Geel electron Linacs showed systematic discrepancy in the resonance neutron width estimation. The two sets of data are comprehensively reanalyzed by a shape least-squares method that builds up a single system of normal equations. An accurate resolution function description was obtained by Monte Carlo calculation of the moderation and detection contributions. The two experiments are found to be in complete agreement and a single set of resonance neutron widths is obtained.