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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.
V. Drüke, H. Schaal
Nuclear Science and Engineering | Volume 109 | Number 3 | November 1991 | Pages 297-303
Technical Paper | doi.org/10.13182/NSE91-A23854
Articles are hosted by Taylor and Francis Online.
Fast neutron moderators are often used at intense accelerator-based neutron sources. It is known that grooved moderators provide greater neutron leakage currents than full moderators with flat surfaces of the same volume. Experimentalists are mainly interested in the neutron fluxes at the end of the flight paths, where experiments are normally located. To show that an optimized design of such assemblies can be done by Monte Carlo simulation, a moderator/flight-path assembly was built, and experiments were performed with different surfaces of the fast moderator. The Monte Carlo calculations fit the experiments with sufficient accuracy.