Study on flow induced vibration evaluation for a large scale JSFR piping, 1; Current status of flow induced vibration evaluation for hot-leg piping

大型JSFR用配管の流動励起振動評価研究,1; ホットレグ配管の流動励起振動評価の現況

山野 秀将   ; 堺 公明; 田中 正暁  ; 佐郷 ひろみ*; 廣田 和生*; Xu, Y.*

Yamano, Hidemasa; Sakai, Takaaki; Tanaka, Masaaki; Sago, Hiromi*; Hirota, Kazuo*; Xu, Y.*

This paper describes the current status of flow-induced vibration evaluation for the primary cooling piping in Japan Sodium-cooled Fast Reactor (JSFR), with particular emphasis on research and development activities for the hot-leg piping characterized by a short-elbow piping. Important factors were discussed in evaluating the flow-induced vibration for the hot-leg piping, to which the coolant flows from the reactor upper sodium plenum. To investigate a complex flow near the inlet of the hot-leg piping, a reactor scale numerical analysis was carried out for the reactor upper plenum flow, which was simulated in a 1/10-scale reactor upper plenum experiment. Based on this analysis, experimental conditions on swirl inflow and deflected inflow that were identified as important factors were determined for flow-induced vibration experiments simulating only the hot-leg piping. In this study, the effect of the swirl inflow on flow pattern and pressure fluctuation onto the pipe wall was investigated in a 1/3-scale hot-leg pipe experiment.