The Effect Of Turbulence Models On Coolant Temperature And Velocity For The Pebble-Bed Typed High Temperature Reactor


The 3D thermal-hydraulics analysis based on Computational Fluid Dynamics (CFD) has a role to analysis more detail the reactor safety, especially for pebble-bed typed High Temperature Reactor (HTR). A realistic pebble arrangement becomes a challenge to be modeled based on the Simple Cubic (SC), Body-Centered Cubic (BCC) and Face-Centered Cubic (FCC). Furthermore, CFD calculation could utilizes laminar model as well as turbulence model such as ,  and Reynold stress model (RSM). Therefore, the objective of this reseach is to analyze the effect of turbulence model on temperature and coolant velocity distribution using FCC on pebble-bed typed HTR as well as investigation of the turbulence models. The comparison shows that all models are acceptable for HTR-10 case with the difference by the range of 0.03-0.33% for the temperature parameters, in which the minimum different is obtained by  model.


[1] Xingqing, J. et al., “Prediction Calculation and Experiments for The First Criticality oh the 10 MW High Temperature Gas-Cooled Reactor-Test Module”, Nuclear Engineering and Design, Vol.218, pp.43-49 (2002).

[2] IAEA-TECDOC-1382, “Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of The HTTR and HTR-10”, IAEA, November, Vienna (2003)

[3] Du Toit, C.G. et al., “A System CFD Model of a Packed Bed High Temperature Gas-Cooled Nuclear Reactor”, International Journal of Thermal Science, Vol.45, pp.70-85 (2006).

[4] Ferng, Y.M. and Chen, C.T., “CFD Investigating Thermal-Hydraulics Characteristic and Hydrogen Generation from Graphite-Water Reaction After SG Tube Rupture in HTR-10 Reactor”, Journal of Applied Thermal Engineering, Vol.31, pp.2430-2438 (2011).

[5] Ferng, Y.M. and Lin, K.Y., “CFD Investigation of Thermal-Hydraulic Characteristics in a PBR Core Using Different Contact Treatments Between Pebbles”, Annals of Nuclear Energy, Vol. 72, pp. 156-165 (2014).

[6] Ferng, Y.M. and Chi, C.W., “CFD Investigating the Air Ingress Accident in A HTGR Simulation of Thermal-Hydraulic Characteristics”, Nuclear Engineering and Design, Vol.245, pp.28-38 (2012).

[7] Ferng, Y.M. and Lin, K.Y., “Investigating Effects of BCC and FCC Arrangements on Flow and Heat Transfer Characteristics in Pebbles Through CFD Methodology”, Nuclear Engineering and Design, Vol.258, pp.66-75 (2013).

[8] Dixon, A.G., et al., “Systematic Mesh Development for 3D CFD Simulation of Fixed Beds: Single Sphere Study”, Journal of Computer and Chemical Engineering, Vol.35, Issue 7, pp.1171–1185 (2011).

[9] Dehbi, A. and Martin, S.,”CFD Simulation of Particle Deposition on An Array of Spheres Using an Euler/Lagrange Approach”, Nuclear Engineering and Design, Vol.241, pp.3121– 3129 (2011).

[10] Yaser, H. and Khosrow, J., “Modeling of Laminar Forced Convection in Spherical-Pebble Packed Beds”, Journal of Mechanical Science and Tech., Vol.26 (2), pp.643-649 (2012).

[11] Pedras, M.H.J. and de Lemos, M.J.S., “Macroscopic Turbulence Modeling for Incompressible Flow through Under-formable Porous Media”, Journal of Heat Mass Transfer, Vol.44, pp.1081-1093 (2001).

[12] Najar, N.A., et al.,”Comparative Analysis of k − and Spalart-Allmaras Turbulence Models for Compressible Flow through a Convergent-Divergent Nozzle”, The International Journal of Engineering and Science (IJES), Vol.2, Issue 8, pp.8-17 (2013)

[13] Wilcox, D.C., “Formulation of The k − Turbulence Model Revisited”, AIAA Journal, Vol. 46, No.11, pp.2823-2838 (2008).

[14] ”Reactor Core Design of High-Temperature Gas-Cooled Reactors. Part 2: Heat Transfer in Spherical Fuel Elements”, KTA 3102.2, Nuclear Safety Standards Commission (KTA), Duetsch (1983).