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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.
D. Kwiat
Nuclear Science and Engineering | Volume 80 | Number 3 | March 1982 | Pages 469-473
Technical Note | doi.org/10.13182/NSE80-469
Articles are hosted by Taylor and Francis Online.
A direct method for the calculation of the chord length distribution function f(l), for special as well as more general geometries, is investigated here. The method is tested against well-known results for sphere and infinite slab. Then, a derivation of P(x), the escape probability function, for an infinite square prism is presented. This method differs from Carlvik's in that, instead of currents into the surface, f(l) is derived here based on geometrical considerations alone. For P(x) we only assume a homogeneous source in fuel.