Critical heat flux of comparatively low-velocity upward-saturated two-phase flow in vertical channels
- Japan Atomic Energy Research Inst., Tokai (Japan)
A quantitative analysis of critical heat flux (CHF) in both vertical circular tubes and rectangular channels under about 0.1 to 14 MPa was successfully carried out by application of the completely separated two-phase flow model to the comparatively low-velocity, upward-saturated two-phase flow, based on an existing model of vapor blanket over the thin liquid sublayer on the heated walls at the CHF point, which was originally proposed by Haramura and Katto. Over 1,000 experimental CHF data were compared with analytical results and it was clarified that the analytical results gave good predictions of the existing experimental results of circular tubes of 3.0 to 7.8 mm in diameter and 0.15 to 0.6 m in length at 0 to 300 K and rectangular channels of 1.03 to 12.7 mm in channel gap and 0.15 to 0.94 m in channel length at 4 to 328 K of inlet subcooling. The differences in characteristics of CHF between circular tubes and rectangular channels in upward-saturated two-phase flow were also identified.
- OSTI ID:
- 215437
- Journal Information:
- Heat Transfer - Japanese Research, Journal Name: Heat Transfer - Japanese Research Journal Issue: 8 Vol. 23; ISSN 0096-0802; ISSN HTJPAU
- Country of Publication:
- United States
- Language:
- English
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