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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. Downar, H. Khalil
Nuclear Science and Engineering | Volume 109 | Number 3 | November 1991 | Pages 278-296
Technical Paper | doi.org/10.13182/NSE91-A23853
Articles are hosted by Taylor and Francis Online.
The uncertainty in the burnup reactivity swing δkb attributable to nuclear data uncertainties is analyzed using depletion-dependent sensitivity coefficients for single- and multicycle equilibrium depletion. Four systems are analyzed with design features that encompass many of the design options considered for current U.S. advanced liquid-metal reactor cores. These systems, while characterized by very different δkb values in the range from —0.22 to 3.87% Δk, exhibit much smaller differences in their δkb uncertainties, which range from 0.18 to 0.33% Δk. The δkb uncertainties depend primarily on the design choices of core size and fissile fuel type, as well as whether the analysis represents multicycle effects. For all reactors analyzed, the burnup swing uncertainty is dominated by the 238U capture reaction. The potential for reducing uncertainties by a factor of 3 by use of available integral experiment results is also demonstrated.