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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.
M. Hayashi, T. Nishigori, R. G. Alsmiller, Jr., R. A. Lillie
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 391-400
Technical Paper | doi.org/10.13182/NSE91-A23864
Articles are hosted by Taylor and Francis Online.
Calculational studies are conducted of neutron and gamma-ray transport in the beam tubes of a proposed high-flux reactor for the Advanced Neutron Source. To avoid excessively long computing times, the calculations were carried out by coupling two, two-dimensional discrete ordinates calculations. The calculational methodology used is briefly described. Calculated results are presented of the thermal neutron, nonthermal neutron, and gamma-ray fluxes in a radial and a tangential beam tube. Both scalar and angular fluxes in and at the exit of the beam tubes are given. When compared with the radial beam tube, the tangential beam tube shows a lower flux of high-energy neutrons and a much lower flux of gamma rays. The spectral characteristics of the particle fluxes at the exits of the beam tubes are similar to those at the entrances.