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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.
M. Corradini, H.H. Reineke
Nuclear Science and Engineering | Volume 102 | Number 3 | July 1989 | Pages 260-282
Technical Paper | doi.org/10.13182/NSE102-260
Articles are hosted by Taylor and Francis Online.
The results from the BETA molten core/concrete interaction (MCCI) experiments conducted at Kernforschungszentrum Karlsruhe (KfK) and the associated analyses using computer models developed by KfK and by Sandia National Laboratories, i.e., WECHSL and CORCON, are described. Two important observations were made in the BETA steady-state tests: The first observation could be modeled by WECHSL and CORCON by modifications when interface heat transfer considered a “transition boiling” analogy model. The second observation was not modeled but is expected to be important during the high-temperature phase of the MCCI when fission product release is of concern. These results suggest that the BETA experiments provide necessary information to validate MCCI models for silicate (basaltic) concrete. For limestone (carbonatic) concrete, there are still open questions that further tests must address.