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Research Papers: Fluid-Structure Interaction

Numerical Simulation of Subcooled Flow Boiling Heat Transfer in Helical Tubes

[+] Author and Article Information
Jong Chull Jo1

 Korea Institute of Nuclear Safety, 19 Kusung-dong, Yusung-gu, Taejon 305-338, Koreajcjo@kins.re.kr

Woong Sik Kim

 Korea Institute of Nuclear Safety, 19 Kusung-dong, Yusung-gu, Taejon 305-338, Korea

Chang-Yong Choi

 Jeonju University, Hyoja-dong, Wansan-gu, Jeonju 560-759, Korea

Yong Kab Lee

 ANST Co. Ltd., Guro-dong, Guro-gu, Seoul 152–847, Korea

1

Corresponding author.

J. Pressure Vessel Technol 131(1), 011305 (Nov 24, 2008) (9 pages) doi:10.1115/1.3028022 History: Received November 19, 2006; Revised August 14, 2007; Published November 24, 2008

This paper addresses the numerical simulation of two-phase flow heat transfer in the helically coiled tubes of an integral type pressurized water reactor steam generator under normal operation using a computational fluid dynamics code. The shell-side flow field where a single-phase fluid flows in the downward direction is also calculated in conjunction with the tube-side two-phase flow characteristics. For the calculation of tube-side two-phase flow, the inhomogeneous two-fluid model is used. Both the Rensselaer Polytechnic Institute wall boiling model and the bulk boiling model are implemented for the numerical simulations of boiling-induced two-phase flow in a vertical straight pipe and channel, and the computed results are compared with the available measured data. The conjugate heat transfer analysis method is employed to calculate the conduction in the tube wall with finite thickness and the convections in the internal and external fluids simultaneously so as to match the fluid-wall-fluid interface conditions properly. Both the internal and external turbulent flows are simulated using the standard k-ε model. From the results of the present numerical simulation, it is shown that the bulk boiling model can be applied to the simulation of two-phase flow in the helically coiled steam generator tubes. In addition, the present simulation method is considered to be physically plausible in the light of discussions on the computed results.

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Copyright © 2009 by American Society of Mechanical Engineers
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References

Figures

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Figure 8

Temperature distributions at the tube wall cross-sections

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Figure 9

Tube-side flow velocities along the tube length

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Figure 10

Tube-side secondary flow velocities along the tube length

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Figure 11

Comparison between the secondary flow field supposed by Owhadi (5) and the CFD calculations by Jo (22)

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Figure 12

Heat transfer coefficients at the inner and outer tube wall surfaces

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Figure 13

Tube-side void and density distributions along the tube length

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Figure 2

Schematic of HCTSG

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Figure 3

CFD analysis model of a helically coiled tube

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Figure 4

Mesh for CFD analysis

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Figure 5

(a) Radially averaged void fractions (Case 1a (14-15)). (b) Radially averaged void fractions (Case 1b (14-15)). (c) Radially averaged void fractions (Case 2a (14-15)). (d) Radially averaged void fractions (Case 2b (14-15)). (e) Radially averaged void fractions (Case 3a (14-15)). (f) Radially averaged void fractions (Case 3b (14-15)). (g) Radially averaged void fractions (Case 4 (14,16)). (h) Radially averaged void fractions (Case 5 (14,16)).

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Figure 6

Typical calculation result of velocity vectors at a vertical symmetry cross-section of the analysis model

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Figure 7

Tube-side fluid void fraction distributions along the tube length

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