2016 Annual Meeting

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Oral Presentation

III. Fission Energy Engineering » 304-1. Thermal Hydraulics, Energy Conversion, Energy Transfer, Energy Storage

[1D01-07] Thermal Hydraulics of Sodium-Cooled Fast Reactors 1

Sat. Mar 26, 2016 10:00 AM - 11:50 AM Room D (Lecture Rooms B B104)

Chair: Minoru Takahashi (Tokyo Tech)

10:00 AM - 10:15 AM

[1D01] Study on Flow-Induced-Vibration Evaluation of Large-Diameter Piping in a Sodium-Cooled Fast Reactor

(45)Visualization of the Flow Field in a Triple Elbow Piping System under Swirling Inflow Conditions

Jun Mizutani1, ＊Shinji Ebara1, Hidetoshi Hashizume1, Hidemasa Yamano2 (1.Tohoku Univ., 2.JAEA)

Keywords:Fast reactor, Flow-Induced Vibration, Swirling flow, Flow separation

次世代ナトリウム冷却高速炉の一次冷却系コールドレグ配管では，強い旋回流が流入し，複雑な乱流場が形成され，剥離渦放出に起因した圧力変動が想定される．本研究では旋回流生成器を用いて，様々な入口旋回流に対するエルボ内部および下流の流れ場を，特に時間平均場について実験的に調べた．