Experimental study of counter-current two-phase flow in horizontal tube connected to inclined riser.

• OHNUKI Akira

  Japan Atomic Energy Research Institute

抄録

In order to determine the Counter-Current Flow Limitation (CCFL) in hot legs of PWRs, CCFL characteristics of air-water and saturated steam-water flow were experimentally investigated in a modeled flow path of a horizontal tube connected to an inclined riser. The ranges of dimensions of experimental tubes were as follows : diameter D 0.0260, 076 m, length of horizontal tube H 0.010.4 m, length of inclined riser I 0.0380.6 m and inclination angle of inclined riser θ 40°or 45°.<BR>Wallis-type correlation (J_g^*1/2+mJ_l^*1/2=C) was applicable to the data during a steady separated flow. An analysis based on envelope theory showed that the constant C should be a function of H/D and I. A function of C with those parameters was empirically determined by using data obtained in this study. The developed function correlated well with the results of Richter el al. (D=0.203m, H=1.26 m, I=0.5 m and θ=45°). The constant m in the Wallis-type correlation was almost constant 0.75. The problems were discussed, which should be made clear to apply the correlation obtained in this study to an actual PWR hot leg.

収録刊行物

• Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌）

  Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌） 23 (3), 219-232, 1986

  一般社団法人 日本原子力学会

キーワード

• counter current
• air
• steam
• water
• PWR type reactors
• loss of coolant
• reactor safety
• horizontal tube
• inclined riser
• two-phase flow
• dimensionless superficial velocity
• parameter effects

詳細情報

• CRID: 1390282679071083648
• NII論文ID: 130000827327
• DOI: 10.3327/jnst.23.219
• COI: 1:CAS:528:DyaL28XhsFOls7w%3D
• ISSN: 18811248
• ISSN: 00223131
• 本文言語コード: en
• データソース種別:
  • JaLC
  • Crossref
  • CiNii Articles
• 抄録ライセンスフラグ: 使用不可