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Report No.

Study on sodium-water reaction phenomena in steam generator of sodium-cooled fast reactor, 24; Development of experiment method for self-wastage behavior due to sodium-water reaction

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

Self-wastage may take place due to corrosion related to chemical reaction between sodium and water in case of water/water vapor leak from the penetration crack on a tube of steam generator (SG) in sodium-cooled fast reactor (SFR). SFR plant and SG would be damaged by self-wastage when the corrosive thinning progressed up to inner wall of tube. Therefore, multi-dimensional sodium-water reaction analysis code has been developing for safety evaluation of SFR SG. The authors have constructed the experimental method to clarify self-wastage behavior using self-wastage experiment rig (SWAT-2R) and test specimen with fine leak hole.



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