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Latest News
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.
L. Giancarli, F. Barbier, T. Flament, M. Futterer, P. Leroy, E. Proust, J. Sannier, X. Raepsaet, A. Terlain, V. Coen, A. Perujo, T. Sample, G. Benamati, P. Agostini
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2075-2080
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30027
Articles are hosted by Taylor and Francis Online.
The European R&D programme in support of the development of water-cooled Pb-17Li blankets for DEMO aims at improving the data base concerning tritium behaviour and compatibility between blanket materials. The four main areas of the experimental programme are structural material corrosion by Pb-17Li, tritium extraction and permeation control, Pb-17Li physico-chemistry, and water/Pb-17Li interaction. This paper describes the most significant results obtained to date in the various experiments performed in Europe and the future programme required to complete the data base by 1994.
