S0802-1-4 エルボ管内非定常流れにおける大規模渦構造の数値解析(原子力システムおよび要素技術(1))

概要

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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. Flow-induced vibration in the short-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 1/3-scale water experiment were conducted to validate an in-house LES code named as MUGTHES for the short-elbow pipe flow and to investigate unsteady flow behavior through the short-elbow. Numerical results showed good agreement with the experimental results. Unsteady flow characteristics in the short-elbow were clarified in relation to the large-scale eddy motion.
2010-09-04