AN INVESTIGATION OF THE PERFORMANCE OF TRISO FUEL AND MOLTEN FLUORIDE SALTS
AN INVESTIGATION OF THE PERFORMANCE OF TRISO FUEL AND MOLTEN FLUORIDE SALTS
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DOI: https://doi.org/10.22533/at.ed.64224240419
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Palavras-chave: Reator de Sal Fundido, FHR, FliBe, FLiNaK, TRISO
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Keywords: Molten salt reactor, FHR, FliBe, FLiNaK, TRISO
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Abstract: Public opinion has reached a growing consensus that nuclear energy could be an inflection point for mitigating global warming and the shortage of natural resources in the future. The energy demand suffers a rapid increase and can duplicate itself up to 2035. Since 2002, Generation IV has researched at least six designs to substitute nuclear power plants with forty years of operation. A fluoride high-temperature reactor is designed to use tri-structural fuel formed of graphite-matrix-coated particles with a mixture of lithium and beryllium fluorides as a coolant, commonly called FLiBe. However, concisely, the heat transfer models applied to nuclear reactors depend on the Prandtl number correlated to coolant and usage conditions. A pebble-bed fluoride-salt-cooled high-temperature reactor, Mark-1, comprises a conceptual project developed at Berkeley in 2016. Then, it performs a theoretical analysis of the core reactor, where we review the thermal properties of fuel and coolant. It compares generation-IV reactor design analysis with options such as heavy liquid metals, coolants, molten salt reactors, and conventional fuels.
- Daniel de Souza Gomes