Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO2 Fuel
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DOI: 10.1080/00295639.2024.2381387
Abstract: Abstract This paper presents a 1200-MW(thermal) advanced sodium-cooled thermal reactor concept that uses online refueling of 3.5% to 9.95% enriched UO2 fuel pin bundles; uses either graphite or beryllium oxide (BeO) as a neutron moderator;… read more here.
Keywords: sodium cooled; fuel; uo2 fuel; enriched uo2 ... See more keywords