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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.
N. Gurvitz, A. Dubi
Nuclear Science and Engineering | Volume 109 | Number 3 | November 1991 | Pages 304-318
Technical Paper | doi.org/10.13182/NSE91-A23855
Articles are hosted by Taylor and Francis Online.
The general direct statistical approach theory is analyzed for single-path cases. Through this analysis, some conclusions are reached about the optimum benefit that may be obtained with geometric splitting as a function of the number of splitting surfaces used. Also, some useful expressions are derived for predicting the optimum splitting parameters in simple cases. The predictions obtained are compared with the results of the general optimization procedure for a number of test cases, and the results of these comparative calculations are reported.