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May 31–June 3, 2026
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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.
A. Hébert , G. Marleau
Nuclear Science and Engineering | Volume 108 | Number 3 | July 1991 | Pages 230-239
Technical Paper | doi.org/10.13182/NSE90-57
Articles are hosted by Taylor and Francis Online.
The self-shielding treatment of resonant isotopes is currently performed in most lattice codes using the Stamm’ler method on simplified one-dimensional geometries. A generalization of this procedure is proposed for self-shielding calculations over the arbitrary two- and three-dimensional geometries typical of most advanced reactor designs. Numerical results are presented for a simple two-region cylindrical cell and for a small pressurized water reactor assembly exhibiting true two-dimensional behavior. The absorption rates obtained after self-shielding are compared with exact values obtained using an elastic slowing-down calculation where each resonance is modeled individually in the resolved energy domain. It is shown that the generalized Stamm’ler method can be applied without loss of accuracy to multidimensional domains.