著者

石谷 嘉英 中村 友道 佐郷 ひろみ 白石 直 渡壁 壽人 此村 守 山口 彰 藤井 正

出版者

一般社団法人日本機械学会

雑誌

年次大会講演論文集 : JSME annual meeting

巻号頁・発行日

vol.2004, no.7, pp.105-106, 2004-09-04

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A 1/3scale flow-induced vibration test facility that simulates a hot-leg piping of the Japanese sodium-cooled fast reactor (JSFR) is used to investigate the pressure fluctuations of the pipe. To evaluate the flow-induced vibrations for the hot-leg and cold-leg pipes, the random force distributions along the pipe and their correlations are estimated. As the result, the power spectrum densities of pressure fluctuations are classified into four sections, the correlation lengths of axial direction into three sections, and the correlation lengths of tangential direction into four sections. The maximum flow-induced random vibration force in the pipe is estimated in the region of flow separation downstream the elbow.