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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.
Nasir M. Mirza, K. O. Ott
Nuclear Science and Engineering | Volume 110 | Number 2 | February 1992 | Pages 168-176
Technical Notes | doi.org/10.13182/NSE92-A23886
Articles are hosted by Taylor and Francis Online.
There is a problem in the neutron flux calculation in regions with a strong spectral transition from epithermal toward thermal. Space-dependent group constants are developed for the thermal range to treat the highly nonseparable space- and energy-dependent flux distribution that characterizes the transition of fast neutron spectra into partially thermalized spectra. The weighting spectra are obtained from a parametric application of the heavy gas model for scattering with absorption cross sections that include the resonances near and below 1 eV. A space dependence is introduced into weighting spectra by relating the parametric solution of the zero-dimensional spectral equation to thermal and epithermal group fluxes obtained from a prior one-dimensional diffusion calculation. Subsequently, space-dependent thermal group constants are generated. The method is implemented in a standard multigroup diffusion code, executed iteratively. This procedure was applied to compact liquid-metal reactor designs having thermalizing reflector regions. The results indicate the effect of global parameters such as the size of the thermalizing reflector on the group constants, which are considerably different from the classical local group constants.