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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.
Hagai Shaked
Nuclear Science and Engineering | Volume 112 | Number 1 | September 1992 | Pages 95-99
Technical Notes | doi.org/10.13182/NSE92-A23955
Articles are hosted by Taylor and Francis Online.
The absorption probability of neutrons in a cylindrical sample is considered. The neutron beam is monochromatic and collimated, and its intensity is uniform across the beam. A uniform (one-region) sample and a nonuniform (concentric two-region) sample are considered. An exact solution in an analytic form is found for the uniform case. In the nonuniform case, the exact solution is given in the form of an integral (which should be numerically integrated). In the nonuniform sample, concave (i.e., low in the center) and convex distributions of absorber are considered. Some symmetry in the change in the absorption probability due to the absorber nonuniformity with respect to these types of absorber distributions is pointed out and discussed. The applicability and limitations of the solutions are discussed, and an application example is given.