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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.
G. Reffo, F. Fabbri, K. Wisshak, F. Käppeler
Nuclear Science and Engineering | Volume 80 | Number 4 | April 1982 | Pages 630-647
Technical Paper | doi.org/10.13182/NSE82-A18974
Articles are hosted by Taylor and Francis Online.
The capture cross sections of 93Nb, 103Rh, and 181Ta were measured in the 10- to 70-keV neutron energy range, using 197Au as a standard. Most of the data points were obtained with a total uncertainty of ∼4%. This was possible because the calculation of capture gamma-ray spectra allowed reducing the most severe systematic uncertainties involved. Hauser-Feshbach calculations were performed that yielded not only the neutron cross sections of the isotopes considered up to 4-MeV neutron energy but also partial capture cross sections and capture gamma-ray spectra. For these calculations a consistent set of input parameters was determined from available experimental information or from model-guided systematics. The influence of these parameters on the results is discussed.