A three-dimensional computational fluid dynamics model with the thermal phase change model is used to investigate the thermal–hydraulic characteristics of a steam generator with and without quatrefoil tube support plates. The two types of modeled designs are a unit pipe with and one without tube support plates. The computational fluid dynamics simulations capture the boiling phenomena, vortex and recirculation distributions, and the periodic characteristics of the circumferential wall temperature in the regions surrounding the tube support plates. The cross-flow energy responsible for flow-induced vibration damage in the region of the U-bend tubes is obtained with the aid of these localized thermal–hydraulic distributions. A comparison between the key parameters of the unit pipe models with and without tube support plates clearly reveals the influence of tube support plates in guiding flow behavior and alleviating flow-induced vibration damage for a steam generator’s U-bend tube bundle. Therefore, this computational fluid dynamics model can provide technical support for optimizing tube support plate design and improving the thermal–hydraulic characteristics of steam generator.
HassanMAWeaverDSDokainishMA. The effects of support geometry on the turbulence response of loosely supported heat exchanger tubes. J Fluids Struct2003; 18: 529–554.
2.
Axisa F, Desseaux A and Gibert R. Experimental study of tube/support impact forces in multi-span PWR steam generator tubes. In: Proceedings of symposium on flow-induced vibrations, ASME winter annual meeting, New Orleans, New York, 1984, pp. 139–148.
Cattant F. Tests and analyses performed on: tube + tube support plate assemblies removed from a retired steam generator. In: International conference of control of corrosion on the secondary side of steam generators, Airlie, Virginia, October 9–13, 1996, pp.457–472.
5.
AbellàJBalachovIMacdonaldDD. Transport processes in steam generator crevices. III. Experimental results. Corros Sci2002; 44: 191–205.
6.
YangYLSunBZYangLB. Numerical simulation on vapor-liquid two-phase flow of the secondary circuit in steam generator. Atomic Energy Sci Technol2012; 1: 52–57. in Chinese).
7.
FerngYMMaYP. Thermal-hydraulic simulation of localized flow characteristics in a steam generator. Nucl Technol2000; 136: 186–194.
8.
FerngYMChangHJ. CFD investigating the impacts of changing operating conditions on the thermal-hydraulic characteristics in a steam generator. Appl Therm Eng2008; 28: 414–422.
9.
JoJCShinWK. Fluidelastic instability analysis of operating nuclear steam generator U-tubes. Nucl Eng Des1999; 193: 55–71.
10.
JoJCJhungMJKimWS. Dynamic characteristics of steam generator U-tubes with defect. Nucl Eng Des2005; 235: 821–831.
11.
DaiYLLiZAWangCH. Numerical analysis of flow field in shell side of cinquefoil orifice-baffle support type heat exchanger. J Shenyang Inst Chem Technol2007; 21: 26–27.
12.
LiuMSLiuTDongQW. Application of modal analysis in design of steam generator support plate. Nucl Power Eng2008; 29: 48–51.
13.
KimHSJinTEKimHD. Restraining effect of support plates on the limit loads for circumferential cracks in the steam generator tube. Nucl Eng Des2008; 238: 135–142.
14.
Bajorek SM and Helton DM. Numerical modeling of steam generator crevice thermal-hydraulics. Report NUREG/CP-0189, EPRI 1009355, ANL-03/24, 2002.
15.
HassanMAHayderM. Modeling of fluidelastic vibrations of heat exchanger tubes with loose supports. Nucl Eng Des2008; 238: 2507–2520.
16.
HassanMARogersRJGerberAG. Damping-controlled fluidelastic instability forces in multi-span tubes with loose supports. Nucl Eng Des2011; 241: 2666–2673.
17.
Park CY and Lee YS. A prediction method of wear depth considering the gap between tube and support in steam generator. In: The 18th international conference on structural mechanics in reactor technology, Beijing, China, 2005, pp. 4132–4140.
18.
EngelhardtGRMacdonaldDDMilletPJ. Transport processes in steam generator crevices. II. A simplified method for estimating impurity accumulation rates. Corros Sci1999; 41: 2191–2211.
19.
FrickerA. Numerical analysis of the fluid-elastic vibration of a steam generator tube with loose support. J Fluids Struct1992; 6: 85–107.
20.
KimHKLeeYH. Characteristic of slipping behaviour in vibratory wear of a supported tube. Wear2005; 259: 337–348.
21.
PalanisamyRLordW. Finite element simulation of support plate and tube defect eddy current signals in steam generator NDT. Mater Eval1981; 39: 651–655.
22.
DingXS. Natural circulation steam generator operating principles and operating parameters. Nucl Power Plant2003; 2: 15–21. in Chinese).
23.
PatankarSV. Numerical heat transfer and fluid flow, New York: Hemisphere Publishing Corp, 1981, pp. 63–106.
24.
SatoYSekoguchiK. Liquid velocity distribution in two-phase bubble flow. Int J Multiphase Flow1975; 2(1): 79–95.
25.
ChenEFLiYZChengXH. CFD simulation of upward subcooled boiling flow of refrigerant-113 using the two-fluid model. Appl Therm Eng2009; 29: 2508–2517.
26.
ANSYS Inc. ANSYS CFX-12.0 User Manual, 2009.
27.
PrakashC. Two-phase model for binary solid-liquid phase change, part I: governing equations. Numer Heat Transfer Part B1990; 18: 131–131.
28.
GreenSJHetsroniG. PWR steam generators. Int J Multiphase Flow1995; 21: 1–97.
29.
Sha WT and Launder BE. A general model for turbulent, momentum and heat transfer in liquid metals. Paper ANL-77-78, 1979.
30.
LiuCCFerngYM. Numerically simulating the thermal-hydraulic characteristics within the fuel rod bundle using CFD methodology. Nucl Eng Des2010; 240: 3078–3086.
31.
Yao YG 2007. Study about thermal hydraulic static characteristics calculation of nuclear steam generator. Master's Thesis, Shanghai Jiao Tong University, Shanghai, China.
32.
DingXS. Thermal and hydraulic characteristics of a vertical natural circulation nuclear steam generator. Nucl Power Eng1983; 4: 24–31. in Chinese).
33.
AxisaFAndunesJVillardB. Overview of numerical methods for predicting flow-induced vibration. J Press Vess Technol1988; 110: 6–6.
34.
Pettigrew MJ, Taylor CE and Subash N. Flow-induced vibration specifications for steam generators and liquid heat exchangers. Report, AECL-11401, November 1995.
35.
DingXSYangBC. Eddy current inspection of Daya Bay NPP steam generator tubes. Nucl Power Eng1999; 20: 417–420. in Chinese).
36.
Chen J, Zheng CX and Fang SL. Typical defect analysis and quality status evaluation of Daya Bay Nuclear Power Plant steam generator tube. In: Ninth national power systems conference on NDT, Beijing, China, 2003.
