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Effect of swirl inflow on flow pattern and pressure fluctuation onto a single-elbow pipe in Japan Sodium-cooled Fast Reactor

JSFRにおけるシングルエルボ配管への圧力変動と流況に対する旋回流入の影響

山野 秀将; 佐郷 ひろみ*; 廣田 和生*; 早川 教*; Xu, Y.*; 田中 正暁; 堺 公明

Yamano, Hidemasa; Sago, Hiromi*; Hirota, Kazuo*; Hayakawa, Satoshi*; Xu, Y.*; Tanaka, Masaaki; Sakai, Takaaki

JSFR1次冷却系配管のための流力振動評価手法開発の一環として、ホットレグ配管の流力振動評価において重要な因子を論じた。ホットレグ配管入口近くの複雑な流れを調べるため、1/10縮尺炉上部プレナム試験を模擬した数値解析が実施された。この解析に基づき、重要因子として旋回流と偏流が同定され、それらに関する実験条件がホットレグ配管のみを模擬した流力振動実験のために定められた。本研究では、配管への圧力変動と流動状況に対する旋回流入の影響を1/3縮尺ホットレグ配管試験で調べた。その実験から、旋回流によって流動剥離領域はわずかに影響を受けるものの、圧力変動に対しては有意ではないことが示された。本論文ではホットレグ配管への適用性に着目して、流動シミュレーションの結果もまた述べられる。

As part of the development of a flow-induced vibration evaluation methodology for the primary cooling piping in Japan Sodium-cooled Fast Reactor, important factors were discussed in evaluating the flow-induced vibration for the hot-leg piping. To investigate a complex flow near the inlet of the hot-leg piping, a reactor scale numerical analysis was carried out for the reactor upper plenum flow, which was simulated in a 1/10-scale reactor upper plenum experiment. Based on this analysis, experimental conditions on swirl inflow and deflected inflow that were identified as important factors were determined for flow-induced vibration experiments simulating only the hot-leg piping. In this study, the effect of the swirl inflow on flow pattern and pressure fluctuation onto the pipe wall was investigated in a 1/3-scale hot-leg pipe experiment. The experiment has indicated less significant for the pressure fluctuations, while the flow separation region was slightly influenced by the swirl flow. Computational fluid dynamics simulation results also appear in this paper, focusing on its applicability to the hot-leg piping experiments.

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