0
Research Papers

Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows

[+] Author and Article Information
Michio Murase

Mem. ASME Institute of Nuclear Safety System, Inc.,
64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan
e-mail: murase@inss.co.jp

Ikuo Kinoshita

Institute of Nuclear Safety System, Inc.,
64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan
e-mail: kinoshita@inss.co.jp

Takayoshi Kusunoki

Institute of Nuclear Safety System, Inc.,
64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan
e-mail: kusunoki.takayoshi@inss.co.jp

Dirk Lucas

Helmholtz–Zentrum Dresden–Rossendorf,
P.O. Box 510 119, Dresden 01314, Germany
e-mail: d.lucas@hzdr.de

Akio Tomiyama

Kobe University,
1-1 Rokkodai, Nada-ku, Kobe-shi, Hyogo 657-8501, Japan
e-mail: tomiyama@mech.kobe-u.ac.jp

1Corresponding author.

Manuscript received February 17, 2015; final manuscript received July 5, 2015; published online September 3, 2015. Assoc. Editor: Mark Anderson.

ASME J of Nuclear Rad Sci 1(4), 041009 (Sep 03, 2015) (9 pages) Paper No: NERS-15-1019; doi: 10.1115/1.4031032 History: Received February 17, 2015; Accepted July 07, 2015; Online September 16, 2015

One-dimensional (1D) sensitivity computations were carried out for air–water countercurrent flows in a 1/15-scale model of the hot leg and a 1/10-scale model of the pressurizer surge line in a pressurized water reactor (PWR) to generalize the prediction method for countercurrent flow limitation (CCFL) characteristics in slightly inclined pipes with elbows. In the 1D model, the wall friction coefficient fwG of single-phase gas flows was used. The interfacial drag coefficient of fi=0.03, an appropriate adjustment factor of NwL=6 for the wall friction coefficient fwL of single-phase liquid flows (NwG=1 for fwG of single-phase gas flows), and an appropriate adjustment factor of Nde=6 for the pressure loss coefficient ζe of elbows in single-phase flows were determined to give good agreement between the computed and measured CCFL characteristics. The adjusted factors were used to compute and then discuss effects of the inclination angle and diameter on CCFL characteristics.

FIGURES IN THIS ARTICLE
<>
Copyright © 2015 by ASME
Your Session has timed out. Please sign back in to continue.

References

Richter, H. J., Wallis, G. B., Carter, K. H., and Murphy, S. L., 1978, “Deentrainment and Countercurrent Air-Water Flow in a Model PWR Hot-Leg,” U.S. Nuclear Regulatory Commission, .
Mayinger, F., Weiss, P., and Wolfert, K., 1993, “Two-Phase Flow Phenomena in Full-Scale Reactor Geometry,” Nucl. Eng. Des., 145(1–2), pp. 47–61. 10.1016/0029-5493(93)90058-H
Geffraye, G., Bazin, P., Pichon, P., and Bengaouer, A., 1995, “CCFL in Hot Legs and Steam Generators and its Prediction With the CATHARE Code,” Proceedings of the 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-7), Saratoga Springs NY, USA, Sept. 10–15, American Nuclear Society, La Grange Park, IL, pp. 815–826.
Al Issa, S., and Macian, R., 2014, “Experimental Investigation of Countercurrent Flow Limitation (CCFL) in a Large-Diameter Hot-Leg Geometry: A Derailed Description of CCFL Mechanisms, Flow Patterns and High-quality HSC Imaging of the Interfacial Structure in a 1/3.9 Scale of PWR Geometry,” Nucl. Eng. Des., 280, pp. 550–563. 10.1016/j.nucengdes.2014.08.021
Minami, N., Nishiwaki, D., Nariai, T., Tomiyama, A., and Murase, M., 2010, “Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling (I) Air-Water Tests for 1/15-Scale Model of a PWR Hot Leg,” J. Nuclear Sci. Technol., 47(2), pp. 142–148. 10.1080/18811248.2010.9711938
Murase, M., Tomiyama, A., Lucas, D., Kinoshita, I., Utanohara, Y., and Yanagi, C., 2012, “Correlation for Countercurrent Flow Limitation in a PWR Hot Leg,” J. Nucl. Sci. Technol., 49(4), pp. 398–407. 10.1080/00223131.2012.669241
Wallis, G. B., 1969, One-Dimensional Two-Phase Flow, McGraw Hill, New York, pp. 320–339.
Al Issa, S., and Macian, R., 2011, “A Review of CCFL Phenomena,” Ann. Nucl. Energy, 38(9), pp. 1795–1819. 10.1016/j.anucene.2011.04.021
Takeuchi, K., Young, M. Y., and Gagnon, A. F., 1999, “Flooding in the Pressurizer Surge Line of AP600 Plant and Analyses of APEX data,” Nucl. Eng. Des., 192(1), pp. 45–58. 10.1016/S0029-5493(99)00084-9
Cllum, W., Reid, J., and Vierow, K., 2012, “Water Inlet Subcooling Effects on Flooding With Steam and Water in a Large Diameter Vertical Tube,” Proceedings of the 2012 Japan-U.S. Seminar on Two-Phase Flow Dynamics, June 7–12, Tokyo University Marine Science and Technology, Tokyo, T09.
Futatsugi, T., Yanagi, C., Murase, M., Hosokawa, S., and Tomiyama, A., 2012, “Countercurrent Air-Water Flow in a Scale-Down Model of a Pressurizer Surge Line,” Sci. Technol. Nucl. Installations, 2012(2012), pp. 1–7. 10.1155/2012/174838
Doi, T., Futatsugi, T., Murase, M., Hayashi, K., Hosokawa, S., and Tomiyama, A., 2012, “Countercurrent Flow Limitation at the Junction between the Surge Line and the Pressurizer of a PWR,” Sci. Technol. Nucl. Installations, 2012(2012), pp. 1–10. 10.1155/2012/754724
Ohnuki, A., Adachi, H., and Murao, Y., 1988, “Scale Effects on Countercurrent Gas-Liquid Flow in a Horizontal Tube Connected to an Inclined Riser,” Nucl. Eng. Des., 107(3), pp. 283–294. 10.1016/0029-5493(88)90036-2
Kinoshita, I., Murase, M., Utanohara, Y., Lucas, D., Vallée, C., and Tomiyama, A., 2014, “Effects of Shape and Size on Countercurrent Flow Limitation in Flow Channels Simulating a PWR Hot Leg,” Nucl. Technol., 187(1), pp. 44–56.
Taitel, Y., and Dukler, A. E., 1976, “A Model for Predicting Flow Regime Transitions in Horizontal and Near Horizontal Gas-Liquid Flow,” AIChE J., 22(1), pp. 47–55. 10.1002/(ISSN)1547-5905
JSME (Japan Society of Mechanical Engineers), 1991, JSME Mechanical Engineers’ Handbook, Maruzen, Tokyo, pp. A5–79 (in Japanese).
Minami, N., Murase, M., Nishiwaki, D., and Tomiyama, A., 2008, “Countercurrent Gas-Liquid Flow in a Rectangular Channel Simulating a PWR Hot Leg (2) Analytical Evaluation of Countercurrent Flow Limitation,” Jpn. J. Multiphase Flow, 22(4), pp. 413–422 (in Japanese). 10.3811/jjmf.22.413
Utanohara, Y., Kinoshita, I., Murase, M., Minami, N., Nariai, T., and Tomiyama, A., 2011, “Numerical Simulation Using CFD Software of Countercurrent Gas-liquid Flow in a PWR Hot Leg under Reflux Condition,” Nucl. Eng. Des., 241(5), pp. 1643–1655. 10.1016/j.nucengdes.2011.01.051

Figures

Grahic Jump Location
Fig. 1

Experimental setups for the 1/10-scale model of the pressurizer surge line [11]

Grahic Jump Location
Fig. 2

CCFL characteristics in the 1/10-scale model with elbows [11]

Grahic Jump Location
Fig. 3

Flow patterns in the 1/10-scale model with elbows [11]

Grahic Jump Location
Fig. 4

Model for CCFL in an inclined pipe

Grahic Jump Location
Fig. 5

CCFL characteristics in hot leg models (L/D=8.6–9.0)

Grahic Jump Location
Fig. 6

CCFL characteristics in straight pipes without elbows (L/D=63)

Grahic Jump Location
Fig. 7

CCFL characteristics in the 1/10-scale model of the pressurizer surge line with elbows (L/D=63)

Grahic Jump Location
Fig. 8

Effects of inclination angle on CCFL characteristics (Case 3)

Grahic Jump Location
Fig. 9

Effects of diameter on CCFL characteristics computed for Case 3

Grahic Jump Location
Fig. 12

CCFL characteristics in the 1/10-scale model of the pressurizer surge line

Grahic Jump Location
Fig. 11

CCFL characteristics and water levels in the 1/15-scale model of the hot leg

Grahic Jump Location
Fig. 10

Example of measured water velocity fields in a rectangular channel with 150 mm height and 10 mm width

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In