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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. Ihle
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 206-219
Technical Paper | doi.org/10.13182/NSE84-A18578
Articles are hosted by Taylor and Francis Online.
The results of flooding experiments with blocked arrays (FEBA) are presented, a program performed at Kernforschungszentrum Karlsruhe within the framework of the Project Nuclear Safety (PNS). Experiments performed out of pile show that coolant channel constrictions of up to 90% do not lead to significant core coolability problems during reflood. This is even true for low water injection rates corresponding to a flooding velocity of 2 cm/s for the cold bundle. The results of the thermal-hydraulic experiments cover rather widely the cladding temperature range below 1000°C. However, outlining the total range of heat transfer conditions in severely damaged rod bundle geometries, investigations performed within the framework of the PNS are mentioned as well. They provide information about the condition of rod bundles being exposed to temperatures of up to 2000°C prior to reflood.