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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.
T. J. Hoffman, E. U. Vaughan
Nuclear Science and Engineering | Volume 82 | Number 2 | October 1982 | Pages 224-228
Technical Note | doi.org/10.13182/NSE82-A28704
Articles are hosted by Taylor and Francis Online.
The probability table representation of neutron transport in bubbly media, developed by Hoffman and Petrie for neutron flights initiated by collision, is extended to neutron flights initiated at interfaces. Both forms are compared with appropriate Monte Carlo estimates of one-flight transmission through bubbly slabs, with encouraging results for slabs thicker than the bubble diameter. These forms are then combined into a modified probability table method. Application of the modified method to transport calculations requires high spatial and angular resolution but shows that the interface modification can have a substantial effect on calculated bubble worths. Fortunately, the results agree well with the simple Benoist method, which does not require high resolution.