Effects of fluid properties on CCFL characteristics at a vertical pipe lower end
The purpose of this study is to derive a counter-current flow limitation (CCFL) correlation and evaluate its uncertainty for steam generator (SG) U-tubes in a pressurized water reactor (PWR). Experiments were conducted to evaluate effects of the liquid viscosity on CCFL characteristics using air-40 ...
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Veröffentlicht in: | Journal of nuclear science and technology 2015-06, Vol.52 (6), p.887-896 |
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Hauptverfasser: | , , , , , , |
Format: | Artikel |
Sprache: | eng |
Schlagworte: | |
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Zusammenfassung: | The purpose of this study is to derive a counter-current flow limitation (CCFL) correlation and evaluate its uncertainty for steam generator (SG) U-tubes in a pressurized water reactor (PWR). Experiments were conducted to evaluate effects of the liquid viscosity on CCFL characteristics using air-40 wt% or air-60 wt% glycerol water solution and saturated steam-water at atmospheric pressure with vertical pipes simulating the lower part of the SG U-tubes. The steam-water experiments confirmed that CCFL characteristics could be expressed in terms of the Wallis parameters (J
G
* and J
L
*) for the pipe diameters of D = 14, 20, and 27 mm. A CCFL correlation was derived using the ratio μ
G
/μ
L
of the viscosities of the gas and liquid phases, μ
G
and μ
L
, as a correction term representing effects of fluid properties, where J
G
*1/2
(μ
G
/μ
L
)
−0.07
was expressed by a cubic function of J
L
*1/2
(μ
G
/μ
L
)
0.1
. In the correlation, the constant C indicating the value of J
G
*1/2
(μ
G
/μ
L
)
−0.07
at J
L
* = 0 was (1.04 ± 0.05), and this uncertainty of ±0.05 would cover most of the previous experimental data including the ROSA-IV/LSTF data at 1, 3, and 7 MPa. |
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ISSN: | 0022-3131 1881-1248 |
DOI: | 10.1080/00223131.2014.990533 |