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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.
D. J. Brenner, M. Zaider, J. J. Coyne, H.G. Menzel, R. E. Prael
Nuclear Science and Engineering | Volume 95 | Number 4 | April 1987 | Pages 311-315
Technical Note | doi.org/10.13182/NSE87-A20442
Articles are hosted by Taylor and Francis Online.
Neutron cross sections on carbon at and above 14 MeV are of interest for a variety of applications. It is argued that the ENDF/B-V evaluation of the nonelastic cross sections is in some error; this is due in part to the “subtraction” technique used for evaluating the nonelastic cross section, and to an overreliance on old nuclear emulsion data. In addition, secondary uncharged- (and, for biomedical applications, charged-) particle spectra are important. It is shown that kerma-factor calculations are very sensitive to the secondary charged-particle spectrum. Thus an assessment of the reaction mechanisms, leading to evaluated secondary particle spectra, is also needed.