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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.
Seiji Shiroya, Keiji Kanda, Keichiro Tsuchihashi
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 525-537
Technical Paper | doi.org/10.13182/NSE88-7
Articles are hosted by Taylor and Francis Online.
Both experimental and analytical studies have been performed on the temperature coefficient of reactivity in a light water moderated and reflected core loaded with highly enriched uranium fuel at the Kyoto University Critical Assembly. The temperature effect on reactivity was measured for the 20 to 70°C range to investigate separately the effects of the H/235U atomic ratio and the core shape on this quantity. The results of both the eigenvalue and perturbation calculations by the SRAC code system approximately reproduced the experimental data. It was found that the contribution of the core region to the temperature coefficient was negative due to the degradation of moderation, whereas that of the reflector region was positive due to the decrease in neutron absorption. The positive contribution of the reflector region became larger as the H/235U atomic ratio became smaller and the core shape became more slender.