Refine your search:     
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.

Accesses

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.