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Latest News
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.
Gregory D. Spriggs
Nuclear Science and Engineering | Volume 115 | Number 1 | September 1993 | Pages 76-80
Technical Notes | doi.org/10.13182/NSE93-A35525
Articles are hosted by Taylor and Francis Online.
The effective delayed neutron fraction of a solution reactor fueled with highly enriched ura-nyl nitrate was measured using two Rossi-a techniques: the “slope” method and the Nelson number method. The average value of the effective delayed neutron fraction was measured to be 0.0147 ± 13%, which is significantly higher than the calculated value of0.009. The discrepancy between the measured and the calculated value is not understood at this time, but it is suspected that the majority of the bias is associated with the measurement of the intrinsic neutron source strength.
