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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.
Takayuki Terai, Satorn Tanaka, Yoichi Takahashi
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2143-2148
Blanket and Process Engineering | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24600
Articles are hosted by Taylor and Francis Online.
In-situ tritium release behavior from Li2O powder has been investigated under neutron irradiation at high temperatures. It was found that the chemical form of the released tritium depended strongly on the experimental conditions such as pre-treatment (dehumidification) of the sample and the H2 addition to the sweep gas of helium. Water-soluble component was observed to be a main species from the sample pre-dried in N2 stream at 800°C for 3 days, while water-insoluble component had fairly large proportion on the sample pre-dried for 5 days. In the case of He-4%H2 sweep gas, more than 90% of released tritium was water-insoluble even for the sample pre-dried for 3 days. Tritium recovery rate was also accelerated by H2 addition. These experimental results showed that the oxygen activity of the experimental system essentially affected to tritium release behavior from Li2O sample.
