Simulation of natural convection flow for vertical heated rod by using ANSYS/Fluent

Tung Duong Thanh1, Tan Hung Hoang2, Hoang Tuan Truong3, Chi Thanh Tran4, Hiroshige Kikura5
1 s:3:"NTC";
2 Chungnam National university
3 Centre for Nuclear Technologies
4 Vietnam Atomic Energy Institute
5 Tokyo Institute of Technology

Main Article Content

Abstract

The decay heat removal by natural convection is very important in case of Station blackout (SBO) of nuclear reactor. The computational fluid dynamic (CFD) is helpful to simulate the flow and temperature field. However, the CFD simulation models need to be validated by the experimental data. Thus, in this report, the Anslys/Fluent is applied to simulate the natural convection induced by single heater rod. The vertical heated rod with a diameter of 12 mm and a length of 225 mm is immersed at the center of a vertical pipe made of acrylic with a diameter of 146 mm and a height of 500 mm. In this simulation, the coupled scheme algorithm is also applied. Regarding to experimental method, the optical method such as Particle Image Velocimetry (PIV) was applied for 2-dimensional velocity distribution and pointwise temperature measurement. As a result, the predicted flow and temperature field are well agreed with experimental data. Accordingly, the thermal plumes are well estimated by ANSYS/Fluent, in which the buoyant plumes induced by different temperatures vertically go up along the heater rod's upper part until the container's isolated upper wall. The complicated flow occurs in the middle part of the container by mixing the downward flow on the top and the upward flow from the heater rod.

Article Details

References

[1]. IAEA-TECDOC-1474, Natural circulation in water cooled nuclear power plants Phenomena, models, and methodology for system reliability assessments, 2005.
[2]. K. Kitamura , A. Mitsuishi, T. Suzuki, F. Kimura, “Fluid flow and heat transfer of natural convection induced around a vertical row of heated horizontal cylinders”, Int. J. Heat and Mass Transfer 92 (2016) 414-429.
[3]. S. Grafsrønningen, A. Jensen, B.A.P. Reif, “PIV investigation of the buoyant plume from natural convection heat transfer above a horizontal heated cylinder,” Int. J.Heat Mass Transf. 54 (23–24) (2011), pp. 4975–4987.
[4]. Park H, Park J, Jung S.Y: Measurements of velocity and temperature fields in natural convective flows, Int. Journal of Heat and Mass Transfer 139 (2019), 293–302.
[5]. S. Kim, S.U. Ryu, D.-J. Euh, C.-H. Song, “Experimental study on the thermal stratification in a pool boiling with a horizontal heat source”, Ann. Nucl. Energy, 106 (2017), pp. 235–246.
[6]. Nhi-Dien Nguyen, Kien-Cuong Nguyen, Ton-Nghiem Huynh, Doan-Hai-Dang Vo and Hoai-Nam Tran, Conceptual Design of a 10 MW Multipurpose Research Reactor Using VVR-KN Fuel”, Science and Technology of Nuclear Installations, Vol. 2020, Volume 2020, Article ID 7972827, 11 p.p.
[7]. Foroozani N, Krasnov D & Jörg Schumacher, “Turbulent convection for different thermal boundary conditions at the plates” , J. Fluid Mech. 907 (2021), A27
[8]. Seok-Ki Choi, Seo-O Kim, Eui-Kwang Kim, Hoon-Ki choi, “Evaluation of the K-epsilon-VV-F Turbulence Model for Natural Convection in a rectangular cavity”, Journal of Computational Fluids Engineering, 2002.
[9]. Boz Z, Erdogdu F & Mustafa Tutar, “Effects of mesh refinement, time step size and numerical scheme on the computational modeling of temperature evolution during natural-convection heating, Journal of Food Engineering 123 (2014), 8–16.