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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.
P. Barbucci, F. Di Pasquantonio
Nuclear Science and Engineering | Volume 82 | Number 4 | December 1982 | Pages 448-457
Technical Note | doi.org/10.13182/NSE82-A21458
Articles are hosted by Taylor and Francis Online.
An evaluation of the computational efficiency of some spatial discretization schemes has been carried out on a number of slab geometry problems of interest in the shielding field. The achievable accuracy for a given cost of the calculation was compared, taking into account that the actual cost depends on both the computing time and the storage required and using as an error measure the ratio to the “reference solution” for a global quantity like the dose rate or the fast flux. The examined cases include neutron calculations in water, concrete, and steel slabs and, in a pressurized water reactor system, the photon calculations in a lead slab. The main conclusion of the study is that, for a given cost, the exponential scheme supplies solutions more accurate than those of the linear characteristic scheme or, at least, of the same quality.