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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.
D. Ingman, E. Taviv
Nuclear Science and Engineering | Volume 85 | Number 1 | September 1983 | Pages 26-35
Technical Paper | doi.org/10.13182/NSE83-A17148
Articles are hosted by Taylor and Francis Online.
The applicability and parameters of the image method for solving the thermal neutron leakage distribution on the plane surface of the semi-infinite hydrogen-containing medium in the case of the neutron field originating from a point source of fast neutrons is investigated. The research performed has shown that for the use of the image method it is necessary to introduce not only the concept of the effective extrapolated boundary but also the concept of an effective origin of the point source of fast neutrons. The values of effective extrapolated length and effective location of the point source were calculated and examined by experiment for pure water.
