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 ("Short-elbow") has been conducted. Structural integrity of the pipe due to the flow instability around the short-elbow is concerned in the design study of JSFR. In this paper, background of the study and outline of the numerical investigations for the structural integrity of the pipe elbow are briefly described. Numerical results at Re=5x10^5 and Re=3.7x10^6 in the short-elbow are presented as a verification study of the in-house LES code named as MUGTHES. Flow characteristics around the elbow exit and influence of the inlet boundary condition on them are discussed.
