NUMERICAL APPROACH FOR QUANTIFICATION OF SELFWASTAGE PHENOMENA IN SODIUM-COOLED FAST REACTOR

Sodium-cooled fast breeder reactors use liquid sodium as a moderator and coolant to transfer heat from the reactor core. The main hazard associated with sodium is its rapid reaction with water. Sodium-water reaction (SWR) takes place when water or vapor leak into the sodium side through a crack on a...

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Bibliographic Details
Published inNuclear engineering and technology Vol. 47; no. 6; pp. 700 - 711
Main Authors JANG, SUNGHYON, TAKATA, TAKASHI, YAMAGUCHI, AKIRA, UCHIBORI, AKIHIRO, KURIHARA, AKIKAZU, OHSHIMA, HIROYUKI
Format Journal Article
LanguageKorean
Published 2015
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