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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.
T. Takeda, T. Umano
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 1-10
Technical Paper | doi.org/10.13182/NSE85-5
Articles are hosted by Taylor and Francis Online.
A practical formula for sensitivity coefficients of burnup properties has been derived by means of a generalized perturbation theory. A differential method is employed. The resultant formula corresponds to an extension of the Williams formula, which is based on a variational method. The applicability of the proposed formula is investigated by calculating sensitivity coefficients in a typical fast breeder reactor and by comparing the results with those from the direct subtraction calculations. The physical meanings of components of the coefficients are discussed.