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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
V. E. Raevskaya
Nuclear Science and Engineering | Volume 94 | Number 4 | December 1986 | Pages 393-408
Technical Paper | doi.org/10.13182/NSE86-A18349
Articles are hosted by Taylor and Francis Online.
A method for the calculation of the neutron flux in one-group P3 approximation in a reactor polycell with multizone annular clusters is presented. The cluster central zone contains multizone fuel rods. The rod and cluster neutron fluxes are assumed to be azimuthally symmetrical. Four moments in the scattering function are taken into account. The CLUST code has been developed for computing the neutron fluxes in a reactor polycell. Its numerical results are compared with those of the other codes and appear to be in good agreement with them.
