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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.
W. T. Urban, T. J. Seed, Donald J. Dudziak
Fusion Science and Technology | Volume 2 | Number 2 | April 1982 | Pages 261-271
Technical Paper | Shielding | doi.org/10.13182/FST82-A20759
Articles are hosted by Taylor and Francis Online.
A nucleonic analysis of the Engineering Test Facility vacuum pumping (VP) duct shield has been performed using a coupled Monte Carlo/discrete ordinates method. This method used Monte Carlo to determine internal and external boundary surface sources for subsequent use in discrete ordinates calculations of the neutron and gamma-ray transport through the shield. Confidence in both the coupled method and the results obtained through its use was provided through comparisons with three-dimensional Monte Carlo results. Calculations in the toroidal plasma chamber and the neutral beam injector duct, which were required prior to the VP duct shield calculations, are also described.