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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.
R. Roy, A. Hébert, G. Marleau
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 112-128
Technical Paper | doi.org/10.13182/NSE93-A28522
Articles are hosted by Taylor and Francis Online.
The integral transport equation is solved in periodic slab lattices in the case where a critical buckling search is performed. First, the angular flux is factorized into two parts: a periodic microscopic flux and a macroscopic form with no angular dependence. The macroscopic form only depends on a buckling vector with a given orientation. The critical buckling norm along with the corresponding microscopic flux are obtained using anisotropic collision probability calculations that are repeated until criticality is achieved. This procedure allows the periodic boundary conditions of slab lattices to be taken into account using closed-form contributions obtained from the cyclic-tracking technique, without resorting to infinite series of exponential-integral evaluations. Numerical results are presented for one-group heterogeneous problems with isotropic and anisotropic scattering kernels, some of which include void slit regions.