抄録
In Japan Atomic Energy Agency (JAEA), a study on flow induced vibration in the primary cooling system of Japan Sodium cooled Fast Reactor (JSFR) consisting of large diameter pipe and pipe elbow with short curvature radius has been conducted. Flow-induced vibration in the elbow 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 Re=5×10^5 through the short-elbow pipe (Rc/D=1) which curvature radius Re corresponded to pipe diameter D was conducted to validate an in-house LES code named as MUGTHES for the pipe elbow flow and to investigate pressure fluctuation generation mechanism related to unsteady flow in a short-elbow pipe.
