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Steam-water pressure drop under high pressure condition

高圧条件下での気液圧力損失

Liu, W.; 玉井 秀定; 吉田 啓之; 高瀬 和之; 早船 浩樹; 二神 敏; 木曽原 直之

Liu, W.; Tamai, Hidesada; Yoshida, Hiroyuki; Takase, Kazuyuki; Hayafune, Hiroki; Futagami, Satoshi; Kisohara, Naoyuki

原子力機構では、次世代FBRで採用が検討されている、直管型蒸気発生器(SG)の熱設計手法を構築するため、高圧条件下で試験を実施し、圧力損失を含む詳細な二相流データを取得するとともに、各種相関式の評価を行っている。本研究では、これらの高圧試験を模擬した解析を行い、二相流による圧力損失の増加割合を与える二相増倍係数相関式であるMartinnelli-Nelson式,Friedel式,Chisholm式,Hancox式及び均質流モデルに対して、それぞれの予測性能を評価した。一連の評価の結果、二相増倍係数相関式にChisholm式を用いることより、40g/s$$sim$$200g/sの広い流量範囲で二相流の圧力損失を予測できることがわかった。

For the Steam Generator (SG) in a commercialized sodium cooled faster breeder reactor, flow instability in water side is one of the most important items need researching. As the first step of the research, thermal hydraulics experiments using water as test fluid were performed under high pressure condition at JAEA with using a circular tube. Pressure drop, heat transfer coefficients and void fraction data were derived. This paper focuses on the discussion to steam - water pressure drop. We evaluated existing correlations for two-phase flow multiplier under high pressure. As a result, Chismholm correlation was confirmed being the best one for the present high pressure data.

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