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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.
Felix C. Difilippo
Nuclear Science and Engineering | Volume 107 | Number 1 | January 1991 | Pages 82-98
Technical Note | doi.org/10.13182/NSE91-A23782
Articles are hosted by Taylor and Francis Online.
Because of the demand for intense neutron beams for applications in basic and applied sciences, several design concepts have appeared in the literature recently. It is, therefore, appropriate to present a theory that connects the large variety of possible designs in order to individualize the main parameters from the neutronic point of view; the theory is validated with results from numerical analysis that simulate the transport of neutrons in such drastically different systems as spallation and fission sources. The theory is used to present scoping studies for the production of thermal neutron fluxes around and beyond 1020/m2·s.
