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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.
Kostadin Dinov, Chihiro Matsuura, Daisuke Hiroishi, Kenkichi Ishigure
Nuclear Science and Engineering | Volume 113 | Number 3 | March 1993 | Pages 207-216
Technical Paper | doi.org/10.13182/NSE92-36
Articles are hosted by Taylor and Francis Online.
The solubility of NiO and CoO in high-temperature water is measured at temperatures between 373 and 523 K in a special batch autoclave system. Great importance has been given to deriving reliable thermodynamical data for the related ionic species at elevated temperatures. The experimental results for NiO seem to be consistent with the previously proposed free-energy data set for Ni2+. Because of the lack of experimental information on the free energy of formation (ΔG°f) for Co2+, the Criss-Cobble approach is used to calculate the values. The estimates are compared with the experimental results. It is concluded that the application of the Criss-Cobble procedure to Co2+ ions is not correct above 423 K. Based on the experiments, a new set of ΔG°f values for Co2+ is proposed.