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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.
Nobuyuki M. Masaki, Takakuni Hirabayashi, Masakatsu Saeki
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 1337-1342
Tritium Technology | doi.org/10.13182/FST89-A39874
Articles are hosted by Taylor and Francis Online.
Behavior of sorption of tritium on surfaces of stainless steel, aluminum and borosilicate glass has been studied using gaseous tritium with high specific activity and the newly obtained knowledge has been applied to chemical and thermal decontamination of tritium-sorbing materials. The behavior depends on a character of surface of each material. The total amount of sorbed-tritium is evaluated as a function of time of exposure to gaseous tritium. The depth-profile of sorbed-tritium is obtained by chemical etching method. From these results, practical samples of stainless steel were decontaminated. The vacuum-bakeout for 21, hours at 773 K and dissolution by dilute (5%) HCl for 2 hours enable us to obtain the decontamination factor of 200.