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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.
Keisuke Kobayashi and Tsuyoshi Misawa
Nuclear Science and Engineering | Volume 92 | Number 3 | March 1986 | Pages 407-420
Technical Paper | doi.org/10.13182/NSE86-A17529
Articles are hosted by Taylor and Francis Online.
It is shown that the semi-discrete ordinates equation can be used to create a computer program for a general order of PL approximations for solving the multigroup neutron transport equation in two-dimensional x-y geometry. Sample calculations for problems using up to a P7 approximation and up to four energy groups are given, and the results are compared with corresponding ones obtained by the discrete ordinates method. As the order of approximations increases, both results show good agreement, when the influence of the ray effect is not appreciable. The advantage of the present method is that the ray effect does not occur, which is the problem in the discrete ordinates method.