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 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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February 2009
Research Papers
Numerical Simulation of Subcooled Flow Boiling Heat Transfer in Helical Tubes
Jong Chull Jo,
e-mail: jcjo@kins.re.kr
Jong Chull Jo
Mem.ASME
Korea Institute of Nuclear Safety
, 19 Kusung-dong, Yusung-gu, Taejon 305-338, Korea
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Woong Sik Kim,
Woong Sik Kim
Korea Institute of Nuclear Safety
, 19 Kusung-dong, Yusung-gu, Taejon 305-338, Korea
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Chang-Yong Choi,
Chang-Yong Choi
Jeonju University
, Hyoja-dong, Wansan-gu, Jeonju 560-759, Korea
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Yong Kab Lee
Yong Kab Lee
ANST Co. Ltd.
, Guro-dong, Guro-gu, Seoul 152–847, Korea
Search for other works by this author on:
Jong Chull Jo
Mem.ASME
Korea Institute of Nuclear Safety
, 19 Kusung-dong, Yusung-gu, Taejon 305-338, Koreae-mail: jcjo@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, KoreaJ. Pressure Vessel Technol. Feb 2009, 131(1): 011305 (9 pages)
Published Online: November 24, 2008
Article history
Received:
November 19, 2006
Revised:
August 14, 2007
Published:
November 24, 2008
Citation
Jo, J. C., Kim, W. S., Choi, C., and Lee, Y. K. (November 24, 2008). "Numerical Simulation of Subcooled Flow Boiling Heat Transfer in Helical Tubes." ASME. J. Pressure Vessel Technol. February 2009; 131(1): 011305. https://doi.org/10.1115/1.3028022
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