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Report No.

Study on sodium-water reaction phenomena in steam generator of sodium-cooled fast reactor, 35; Wastage enlargement behavior due to self-wastage experiment

Shimoyama, Kazuhito; Kurihara, Akikazu; Kikuchi, Shin; Umeda, Ryota; Ohshima, Hiroyuki

Corrosion may proceed on the tube surface due to chemical reaction between sodium and water (self-wastage), in case of water/steam leak though the penetrating crack caused in the steam generator tube of sodium-cooled fast reactor. We performed the self-wastage experiments under high sodium temperature condition to evaluate the effect of wastage dimension and water leak rate on self-wastage rate in the fine crack in this report.



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