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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.
M. Segev, J. Stepanek
Nuclear Science and Engineering | Volume 108 | Number 2 | June 1991 | Pages 208-213
Technical Note | doi.org/10.13182/NSE91-A23818
Articles are hosted by Taylor and Francis Online.
A computer routine was written to enable an efficient, yet accurate, interpolation of the basic probabilities required in integral transport calculations of single lattice, as well as multicell, structures. These are The tables within which the routine interpolates contain remainders between accurate probabilities to respective analytical approximations. There are ∼4000 entries for a cylindrical or spherical geometry and 50 for slab geometry. The accuracy is generally within a few tenths of a percent relative error for all the probabilities and can be much lower. The range of optical thicknesses covered is 0 to 20. All the probabilities required for a given layer can be generated on a CRA Y-XMP in a 5 × 10-6 s. A single Dancoff probability can be generated in ∼2.7 × 10-6 s.