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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. H. J. J. van der Hagen, J. E. Hoogenboom, H. van Dam
Nuclear Science and Engineering | Volume 110 | Number 3 | March 1992 | Pages 237-253
Technical Paper | doi.org/10.13182/NSE92-A23896
Articles are hosted by Taylor and Francis Online.
The sensitivity of a neutron detector to parametric fluctuations in the core of a reactor depends on the position and the frequency of the perturbation. The basic neutron diffusion model for the calculation of this so-called field of view (FOV) of the detector is extended with respect to the dimensionality of the problem and the number of energy groups involved. The physical meaning of the FOV concept is illustrated by means of some simple examples, which can be handled analytically. The possibility of calculating the FOV by a conventional neutron diffusion code is demonstrated. In that case, the calculation in n neutron energy groups leads to 2n modified neutron diffusion equations.