2020
DOI: 10.1016/j.nucengdes.2020.110719
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Experimental studies on metallic fuel relocation in a pin bundle core structure of a sodium-cooled fast reactor

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Cited by 3 publications
(1 citation statement)
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“…A Sodium-Cooled Fast Reactor (SFR) concept is investigated as a representative of advanced reactors with an intermediate (between VHTR and PWR) operating temperature range. The analysis for the SFR is based on the AFR-100 reactor design [72]. A concept of the AFR-100 steam cycle has been developed by Argonne in previous work [73].…”
Section: Sfrmentioning
confidence: 99%
“…A Sodium-Cooled Fast Reactor (SFR) concept is investigated as a representative of advanced reactors with an intermediate (between VHTR and PWR) operating temperature range. The analysis for the SFR is based on the AFR-100 reactor design [72]. A concept of the AFR-100 steam cycle has been developed by Argonne in previous work [73].…”
Section: Sfrmentioning
confidence: 99%