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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.
Min-Fong Su, Shiang-Huei Jiang
Nuclear Science and Engineering | Volume 102 | Number 1 | May 1989 | Pages 64-73
Technical Paper | doi.org/10.13182/NSE88-68
Articles are hosted by Taylor and Francis Online.
A general review of investigations of gamma-ray buildup factors is presented. Gamma-ray buildup factors for a point isotropic source in stratified spherical shields have been calculated using the one-dimensional gamma-ray transport code BIGGI-4T. The behavior of the buildup factor for stratified shields with respect to the behavior for the component materials differs between spherical and slab geometry. In addition to a material change effect, the buildup factor for a point isotropic source in stratified spherical shields suffers a density variation effect, which is much more prominent for configurations of heavier density followed by lighter density. The density variation effect can be eliminated by using a specially adjusted calculation of the stratified shields. It has also been found that energy absorption buildup factors in Goldstein and Wilkins’ data have relatively large uncertainties.