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Tanaka, Masaaki; Ohshima, Hiroyuki
no journal, ,
Flow-induced vibration in the hot-leg piping of Japan Sodium cooled Fast Reactor (JSFR) is an important issue in design study of JSFR, because it may affect to structural integrity of the pipe. In this paper, numerical simulations for turbulent flow at high Reynolds number condition through the short-elbow pipe was conducted to validate an in-house LES code named as MUGTHES and to investigate pressure fluctuation generation mechanism related to unsteady flow in a short-elbow pipe.
Kurihara, Akikazu; Shimoyama, Kazuhito; Hamada, Hirotsugu; Ohshima, Hiroyuki
no journal, ,
no abstracts in English
Umeda, Ryota; Shimoyama, Kazuhito; Kurihara, Akikazu
no journal, ,
In case of the water leak into sodium in a steam generator (SG) of sodium-cooled fast breeder reactors (FBRs), exothermic reaction produces reaction fields in association with high temperature and high corrosive action (sodium-water reaction). Adjacent tubes are damaged due to erosive and corrosive environment of the reaction field. Therefore, it is integral to evaluate such sodium-water reaction phenomena with high accuracy for the safety assessment of FBRs. For the purpose of understanding the wastage mechanism, we developed the new experimental apparatus and established the test procedure in which sodium hydroxide (NaOH) collided with the tube material under high temperature conditions simulating the reaction field.