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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.
P. K. Job, K. Subba Rao, M. Srinivasan
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 293-298
Technical Note | doi.org/10.13182/NSE83-A17798
Articles are hosted by Taylor and Francis Online.
It was shown earlier that nonsolvated crystalline BeH2 could serve as an effective moderator in reducing nuclear critical masses below minima achievable in CH2-moderated systems on account of its (n, 2n) reactivity bonus and higher hydrogen number density. The 9Be cross sections used in these calculations were found to overestimate the (n, 2n) multiplication. The precise (n, 2n) contribution to system reactivity and critical mass in the light of the latest 9Be cross-section data are evaluated. The results show that in the case of BeH2-moderated and BeO-reflected systems, five additional neutrons are born in the reaction multiplication in beryllium per 100 fission neutrons released in the core, resulting in a reactivity gain of ∼4%. The corresponding reduction in critical mass is ∼16%. The critical masses calculated with corrected 9Be cross sections show that the crystalline BeH2-moderated and BeO-reflected systems apparently have the smallest possible theoretical critical masses, namely, 0.180, 0.137, and 0.105 kg for 235U, 233U, and 239Pu, respectively.