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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.
P. A. Finn, E. H. Van Deventer
Fusion Science and Technology | Volume 14 | Number 2 | September 1988 | Pages 783-790
Tritium Properties and Interactions with Material | Proceedings of the Third Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Toronto, Ontario, Canada, May 1-6, 1988) | doi.org/10.13182/FST88-A25230
Articles are hosted by Taylor and Francis Online.
The heterogeneous reaction between oxygen/helium gas, tritium and stainless steel was studied at the back surface of a stainless steel tube. The yield of tritiated water was determined as a function of oxygen concentration, tritium concentration, protium concentration, flow rate, and temperature. This report describes the results for two sets of runs done at 550°C with and without 15 ppm protium in the oxygen/helium gas. At oxygen concentrations of 40 ppm, the presence of excess protium in the oxygen/ helium produced a reduced yield of tritiated water. At oxygen concentrations >1000 ppm, the two yields were equivalent, 98%.
