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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.
Esam M. A. Hussein
Nuclear Science and Engineering | Volume 109 | Number 4 | December 1991 | Pages 416-422
Technical Note | doi.org/10.13182/NSE91-A23867
Articles are hosted by Taylor and Francis Online.
Some approximate estimators for obtaining the fluence at a point in Monte Carlo neutron transport calculations are presented and compared with the commonly used next event estimator. These estimators do not require direct evaluation of the scattering probability using Legendre expansions of the differential angular cross sections. The estimators are particularly useful for Monte Carlo programs that sample scattering directions in the center-of-mass coordinate system.