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The 15 th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013 SIMULATION OF SPACER GRID WITH MIXING VANE ON A TYPICAL PWR FUEL ROD BUNDLE SYSTEM USING LATTICE BOLTZMANN METHOD A. Tiftikçi 1 , H. Ayhan 2 , C. Kocar 3 and C.N.Sökmen 4 1,4 Department of Nuclear Engineering, Hacettepe University, Beytepe, 06800, Ankara, Turkey [email protected], [email protected], [email protected], [email protected] ABSTRACT In present paper, the effect of spacer grid on adiabatic single phase flow in a typical nuclear reactor fuel assembly is investigated. Spacer grid with mixing vane of PWR subchannel is simulated. Velocity and pressure profiles for flow around the spacer grid and fuel rod are analysed. Simulation results of 2x2 Pressurized Water Reactor (PWR) rod bundle system with spacer grids and mixing vane are presented. The simulations have been carried out using lattice-Boltzmann method. Flow regime in flow channel is assumed to be laminar and the rod bundle system geometry is nearly realistic. This work offers an alternative way to model nuclear reactor rod bundle system which is the subject of many studies for researchers in order to determine reactor thermal margin and safety. In the near future, turbulent flow regime and heat transfer mechanisms will be adapted to this work. 1. INTRODUCTION Fluid flow around rigid elements is one of the classical problems of fluid mechanics and has been well studied because of its common occurrence in many forms and in different applications [1-3]. These structures can be found both alone and in groups in the designs for heat exchangers, cooling systems for nuclear power plants, offshore structures, power lines, struts, grids, screens and cables in both single and multi-phase flows. A complete understanding of the fluid dynamics for the flow around a kind body includes such fundamental subjects as the boundary layer, separation, the free shear layer, the wake, and the dynamics of vortices. The flow field of multiple-body configurations involves complex interactions between the shear layers, vortices and Karman vortex streets [4]. The problem is further complicated by the large number of configurations encountered in practise, resulting in different flow patterns, and by the effect of their interactions. One of the applications of paramount importance in this study is fluid flow in fuel rod bundles of water nuclear reactors. In this type of nuclear reactors, optimum heat removal from the surface of fuel elements is the subject of many studies for researchers in order to determine reactor thermal margin and safety [5-6]. In these reactors, spacer grids which support the fuel assembly are used as an effective mixing device by attaching various types of flow deflectors. A nuclear fuel spacer grids used for increasing the strength of fuel rod towards the mechanical stress, since fuel rods are about 3.5 m long and coolant flow rate is respectably high. Besides their advantages, they carry some disadvantages such as flow blockage and hence increase in pressure drop across the fuel bundle. Spacers also change convective cooling characteristics. Mixing vane type spacer grids help mixing near this blocked region. The mixing vanes are designed to guide the coolant from one

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The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

SIMULATION OF SPACER GRID WITH MIXING VANE ON A TYPICAL PWR FUEL

ROD BUNDLE SYSTEM USING LATTICE BOLTZMANN METHOD

A. Tiftikçi1, H. Ayhan

2 , C. Kocar

3 and C.N.Sökmen

4

1,4 Department of Nuclear Engineering, Hacettepe University, Beytepe, 06800, Ankara, Turkey

[email protected], [email protected], [email protected],

[email protected]

ABSTRACT

In present paper, the effect of spacer grid on adiabatic single phase flow in a

typical nuclear reactor fuel assembly is investigated. Spacer grid with mixing vane

of PWR subchannel is simulated. Velocity and pressure profiles for flow around

the spacer grid and fuel rod are analysed. Simulation results of 2x2 Pressurized

Water Reactor (PWR) rod bundle system with spacer grids and mixing vane are

presented. The simulations have been carried out using lattice-Boltzmann method.

Flow regime in flow channel is assumed to be laminar and the rod bundle system

geometry is nearly realistic. This work offers an alternative way to model nuclear

reactor rod bundle system which is the subject of many studies for researchers in

order to determine reactor thermal margin and safety. In the near future, turbulent

flow regime and heat transfer mechanisms will be adapted to this work.

1. INTRODUCTION

Fluid flow around rigid elements is one of the classical problems of fluid mechanics and has

been well studied because of its common occurrence in many forms and in different applications

[1-3]. These structures can be found both alone and in groups in the designs for heat exchangers,

cooling systems for nuclear power plants, offshore structures, power lines, struts, grids, screens

and cables in both single and multi-phase flows. A complete understanding of the fluid dynamics

for the flow around a kind body includes such fundamental subjects as the boundary layer,

separation, the free shear layer, the wake, and the dynamics of vortices. The flow field of

multiple-body configurations involves complex interactions between the shear layers, vortices

and Karman vortex streets [4]. The problem is further complicated by the large number of

configurations encountered in practise, resulting in different flow patterns, and by the effect of

their interactions. One of the applications of paramount importance in this study is fluid flow in

fuel rod bundles of water nuclear reactors. In this type of nuclear reactors, optimum heat removal

from the surface of fuel elements is the subject of many studies for researchers in order to

determine reactor thermal margin and safety [5-6].

In these reactors, spacer grids which support the fuel assembly are used as an effective mixing

device by attaching various types of flow deflectors. A nuclear fuel spacer grids used for

increasing the strength of fuel rod towards the mechanical stress, since fuel rods are about 3.5 m

long and coolant flow rate is respectably high. Besides their advantages, they carry some

disadvantages such as flow blockage and hence increase in pressure drop across the fuel bundle.

Spacers also change convective cooling characteristics. Mixing vane type spacer grids help

mixing near this blocked region. The mixing vanes are designed to guide the coolant from one

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

cell to neighbouring cells of the spacer grid, and thus, accomplishing a desired coolant mixing

effect and increasing the thermal allowance of the fuel rods and accomplishing a high

performance fuel assembly.

The mixing-vane type spacer design seen in Figure 1 is to provide vanes that are integrally

formed on the upper edges of the interlaced straps of a grid, and bent over in the flow channel so

as to deflect the upwardly flowing coolant. The vanes are formed in pairs with a slit and recess

between them, such that each vane can be bent in an opposite direction. This design was

optimized for size, strength and corrosion resistance. For typical mixing-vane design, the vane

angle bent from the vertical axis is generally between 20�and 30�. The bent vanes deflect the

coolant to mix between the subchannels of the spaced parallel fuel rods or to swirl within the

subchannel.

Spacer grids are small structures with respect to flow channel (~4% in radial and ~0.2% in

volume). Thus, detailed modelling of fluid flow requires long computational time and powerful

Central Processing Unit (CPU)for Finite Volume Method(FVM) based calculations. Moreover,

geometric decomposition (meshing) can be complicated process for this type of structures. On

the other hand, Cartesian noding (lattice) is used in Lattice-Boltzmann (LB) approach and the

use of this type of nodalization decreases the difficulties of pre-processing. LB method also

requires CPU but nodalization process is easier than Computational Fluid Dynamics (CFD)

calculations. Major drawback of LB method is its stability problem, thus, relatively large number

of iterations are needed until the flow reaches its steady-state behaviour.

The main goal of this study is to achieve successful calculation of flow distribution and pressure

drop in spacer region, since basic calculation of spacer grids is still challenging for CFD

modelling. In addition, this study might be seen as encouraging to model realistic nuclear reactor

rod-bundle systems with an alternative method known as lattice-Boltzmann approach.

2. LATTICE BOLTZMANN MODELS (LBM’S)

Lattice Boltzmann models vastly simplify Boltzmann’s original conceptual view by reducing the

number of possible particle spatial positions and microscopic momenta from a continuum to just

a handful and similarly discretising time into distinct steps. Particle positions are confined to the

nodes of the lattice [7].

Figure 1 – Spacer grids with mixing vane, arches and other elements

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

Figure 2 – D3Q19 x,y and z velocity components

The lattice Boltzmann method is a kinetic-based approach for simulating fluid flows. It

decomposes the continuous fluid flow into pockets of fluid particles which can only stay at rest

or moves to one of the neighbouring nodes. The D3Q19 model (see Figure 2) is one of the

commonly used models in 3D simulation, in which the discrete Lattice-Boltzmann equation is in

the form of;

��� + ��∆ , + ∆ � − ���, � = − �� [���, � − �����, �] (1)

where ���, � is the distribution function for particles with velocity �� at position and time , ∆ is the lattice time interval, �����, � is the equilibrium distribution function and � is the non-

dimensional relaxation time. In the D3Q19 model, the fluid particles have the possible discrete

velocities stated as follows:

�� = ��0,0,0� � = 0�±1,0,0��0, ±1,0� �0,0, ±1� � = 1,2 … 6 �±1, ±1,0��±1,0, ±1��0, ±1, ±1� � = 7,8, … 18 ! The equilibrium function�����, �is written as,

������ = "�#�� $1 + 3 �� ∙ &'( + 92 ��� ∙ &�('* − 32 &('( + �2�

where the weights "� are

"� = , 1/3 � = 01/18 � = 1, 2 … 6 1/36 � = 7,8, … 18! Another term '. represents the sound speed, and it is equal to 1/√3. The relaxation time is

related to the kinematic viscosity in Navier Stokes equation in the form of

0 = 1� − 122 '.(Δ �3�

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

Once the particle density distribution is known, the fluid density and momentum are calculated,

using:

# = 4�����5�67 �4�

& = 1# 4�������5�67 �5�

This simple equation allows us to pass from the discrete microscopic velocities that comprise the

LBM back to continuum of macroscopic velocities representing the fluids motion.

The next steps are streaming and collision of the particles via the distribution function. The

simplest approach uses the Bhatnagar-Gross-Krook Approximation [8] for collision.

3. INCOMPRESSIBLE FLUID FLOW IN LB APPROACH

Lattice Boltzmann (LB) simulations are supposed to represent the physics of an actually existing,

real system. During implementation, the question invariably pops up how to choose the units of

the simulated quantities, the lattice variables. Two constraints determine the choice of units.

First, the simulation should be equivalent, in a well-defined sense, to the physical system.

Second, the parameters should be fine-tuned in order to reach the required accuracy, i.e. the grid

should be sufficiently resolved, the discrete time step sufficiently small and so on [2]

3.1 Governing Equations

In an incompressible fluid, the density takes a constant value # = #7 which does not vary in time

and space. The equations of motion, the Navier-Stokes equations, are governed by the laws for

mass and momentum conservation. The conservation law for mass states that the velocity field is

divergence-less:

∇; ∙ &; = 0 �6�

Here, the index < indicates that variables and derivatives are evaluated in physical units. The

conservation law for momentum leads to the following relation:

=>?&; + @&; ∙ ∇;A&; = − 1#7? ∇;<; + 0;∇;( &; �7�

where <; is the pressure and B; is the kinematic viscosity in physical units.

3.2 Dimensionless Formulation

Equations (6) and (7) are now cast into a dimensionless form. For this, a length scale C7,; and a

time scale 7,; are introduced which are representative for the flow configuration. The length

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

C7could for example stand for the size of an obstacle which is immersed in the fluid, and 7,;

could be the time needed by a passive scalar in the fluid to travel a distance C7,;. The physical

variables such as the time ;and the position D;, are replaced by their dimensionless counterpart:

E = ; 7,; , DE = D;C7,; �8�

In the same manner, a unit conversion is introduced for the other variables, based on a

dimensional analysis:

&; = C7,; 7,; &E , =>? = 1 7,; =>F �9�

∇;= 1C7,; ∇E, <; = C7,;( 7,;( <E �10�

Plugging this change of variables into Equations (6) and (7) leads to the dimensionless version of

the Navier-Stokes equations:

∇E ∙ &E = 0 �11�

=>F&E + �&E ∙ ∇E�&E = −∇E<E + 1G� ∇E( &E �12�

where the dimensionless Reynolds number has been defined as

G� = C7,;( 7,;0; �13�

evaluated in any system of units. Two flows obeying the Navier-Stokes equations are equivalent

if they are embedded in the same geometry (except for a scaling factor) and have the same

Reynolds number.

Note that by expressing reference variables in the dimensionless system, one finds that C7,E = 1

and 7,E = 1. To help intuition, one may therefore consider the dimensionless system as the

system in which C7,; and 7,; are unity. It is also remarked that the viscosity in the dimensionless

system is 0E = 1/G�.

3.3 Discretization of Dimesionless System

The discrete space interval =I is defined as the reference length divided by the number of cells J

used to discretise this length. In the same way, => is defined as the reference time divided by the

number of iteration steps JK>�L needed to reach this time. Recall that both reference variables are

unity in the dimensionless system. Thus, the discretization parameters are

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

=I = 1/J, => = 1/JK>�L �14�

Other variables, such as velocity and viscosity, are easily converted between (D) and (LB)

through a dimensionless analysis:

&E = MIM> &NO , 0E = 1/G� = MI(M> 0NO �15�

and thus,

&NO = =>=I &E , 0NO = =>=I(1G� �16�

Finally, defining the reference velocity &7 = C7/ 7, one finds, by definition

&7,E = 1, &7,NO = =>=I �17�

4. COMPUTATIONAL PROCEDURES AND SETUP

4.1 Geometry Modelling

In present work, 2x2 subchannel of PWR nuclear reactor is modelled by lattice-Boltzmann

approach. The spacer and mixing vanes are treated as very thin surfaces. The other fuel spacer

elements such as the springs are neglected for simplicity because their effect on the flow mixing

is judged to be minimal only inside and near the spacer. The three-dimensional models are

developed by a structured lattice method. The size of the mixing vanes was assumed based on

typical PWR spacers. Cross-sectional view of spacer region is seen in Figure 3.

Figure 3 – Cross sectional view of spacer region

In Figure 3, red regions represent fuel rod; grey region represent spacer arches, mixing vanes and

spacer can; and blue regions represent flow domain.

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

4.2 Boundary and Flow Conditions

Flow is considered to be laminar even if the flow regime in real PWR coolant is turbulent.

Turbulence models are going to be implemented in the near future to our LB model. Flow inlet

velocity is chosen as 1 P/Q and the Reynolds number 500 for this study.The flowing fluid is

water at ambient conditions with average density #7 = 998.2 RS/PT [9].Boundary conditions

are specified as velocity inlet and pressure outlet. Fluid enters the system at the inlet region then

reaches the fuel rods and meets with spacer can. In this region, fluid flows around spacer arches

which touch the fuel rods. Just after fluid leaves the can, it meets with the mixing vane and may

change its direction towards neighbour channel. Channel orientation is presented in Figure 4.

Figure 4 – Fuel rods and mixing vane type spacer grid view

4.3 Mesh

In lattice-Boltzmann method surface mesh is required. Thus, the bundle geometry created is

meshed in STereoLithography (STL) format. Solid surfaces created as STL file are treated as

bounce-back nodes and in fluid-solid interface a bounce-back mechanism is employed. Thus,

solid surface regions are defined as the bounce-back boundary regions. For the nodalization, an

STL geometry seen in Figure 5 is created.

Figure 5 – Surface mesh view (.stl file format)

In calculation phase, code uses cubic lattices. In this work, lattice resolution is chosen as 750 for

flow direction. Thus, 750 x 126 x 126 lattices are created to resolve the bundle geometry with

spacer grid and mixing vane. The number of lattices created resolves the smallest portion of rod

bundle geometry (approximately 2.5 nodes per thinnest component).

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

5. RESULTS AND DISCUSSION

5.1 Velocity Distribution

The simulation results of 2X2 PWR rod bundle system are presented. The flow time 0.267 Q

with time step Δ = 2.6710UV Q is sufficient to reach the steady-state. Velocity profiles for

inlet, spacer outlet and channel outlet regions will be given. Figures (6), (7) and (8) represent

radial velocity distribution of fluid at the entrance of channel, spacer region and at the outlet of

the channel. We can conclude that profiles are reasonable. Fluid flowing through the channel is

distributed when it meets with spacer can. Therefore bulk velocity increases due to decreasing

flow area (sudden contraction). Figure (9) presents vertical velocity comparison for inlet, spacer

and outlet regions. Velocity profile approaches to the profile at inlet region after fluid leaves the

spacer.

Figure 6 – Inlet velocity distribution

Figure 7 – Velocity distribution at spacer region

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

Figure 8 – Outlet velocity distribution

Figure (10) and (11) presents comparison of velocity counters in lateral and longitudinal

directions respectively. From figures, it can be realized that lattice resolutions are sufficient for

this problem. The code can resolve the tiny structures of spacer grid such as arches. Also, the

effects of vanes are seen from Figure 10(e). Flow pattern changed in vane regions.

Figure 9 – Vertical velocity distribution near central region

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

(a) (b) (c)

(d) (e) (f)

Figure 10 – Comparison of velocity distribution. [(a): inlet region, (b): Spacer arches region

(bottom ones), (c): Spacer region (middle), (d): Spacer arches region (top ones),(e): Spacer vane

region, (f): Outlet region

(a)

(b)

Figure 11 – Velocity distributions in flow direction

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

5.2 Pressure Loss at Spacer

Pressure drop ∆W. in spacer region is calculated and compared with the Rehme’s [9] and de

Stordeur’s model [10]. In lattice-Boltzmann approach pressure loss at spacer region is calculated

as,

∆W. = 13 �#.,KX − #.,�Y>� 1ZZ 2( #7

where #.,KX and#.,�Y> are average densities just before and after spacer in LB units respectively, #7 is the physical density of fluid in RS/PT.

Pressure loss at spacer region is also calculated using Rehme’s and de Stordeur’s model for G� = 500 by extrapolation and presented in Table 1.Comparatively, LB results are in good

agreement with Rehme’s model.

Model Rehme de Stordeur LB

∆W. (Pa) 432.145 491.173 423.875

Table 1 – Pressure drop values for spacer

6. CONCLUSION AND FUTURE WORK

It is demonstrated in this study that highly complex fluid flow in a spacer grid with mixing vane

on a typical PWR fuel rod bundle system could be realized with lattice-Boltzmann method.

Simulation results of 2x2 PWR fuel rod bundle system using lattice-Boltzmann method have

been presented. Velocity profiles and pressure drop obtained from the simulations give

reasonable results. Flow geometry with tiny and small grid structures is resolved by the code

using 750 x126x126 lattice points.

The most important conclusion of this study that the complex rod bundle geometry can be

resolved by lattice-Boltzmann framework. Flow around this highly complex geometry is

simulated successfully.The flow regime chosen is not realistic since in PWR systems flow is

turbulent. Fortunately, there is no restriction about the implementation of turbulence models to

the lattice-Boltzmann method. Thus, realistic PWR bundle systems can be modelled with lattice-

Boltzmann approach.

The 15th International Topical Meeting on Nuclear Reactor Thermal - Hydraulics, NURETH-15 NURETH15-324 Pisa, Italy, May 12-17, 2013

7. REFERENCES

[1] D.O.E.Elvis, Y.A. Hassan, “Non-intrusive experimental investigation of flow behaviour

inside a 5x5 rod bundle with spacer grids using PIV and MIR”, Nuclear Engineering and

Design , Vol.239, No.5, 2009, pp. 888-898

[2] S. Jafari,M. Salmanzadeh,M. Rahnama,G. Ahmadi,“Investigation of particle dispersion

and deposition in a channel with a square cylinder obstruction using the lattice Boltzmann

method”, Journal of Aerosol Science, Vol. 41, 2010, pp.198–206

[3] M. Stiebler, M. Krafczyk., S. Freudiger, M. Geiger, “Lattice-Boltzmannlarge eddy

simulation of subcritical flows around asphere on non-uniform grids”, Mesoscopic

Methods for Engineering and Science, Vol.61, No.12,2009, pp. 3476-3484

[4] J. Latt, Choice of units in lattice Boltzmann simulations, 2008, accessed 29 November

2012, <http://wiki.palabos.org/_media/howtos:lbunits.pdf>

[5] H. Ganjiani, B. Firoozabadi,“Three-Dimensional Simulation of Turbulent Flow in 3-Sub

Channels of a VVER-1000 Reactor”, Transaction B: Mechanical Engineering, 2010, Vol.

17, No.2, pp. 83-92

[6] M. Gustzav, P. Jozsef, H. Gabor, “Large eddy simulation of subchannels using the lattice

Boltzmann method”,Annals of Nuclear Energy, Vol.34, No. 1-2, 2007, pp. 140–149

[7] M.C. Sukop, D.T. Thorne, Lattice Boltzmann modelling: an introduction for geoscientists

and engineers, Springer-Verlag, ISBN-13 978-3-540-27981-5, 2005

[8] P.L. Bhatnagar, E.P. Gross, M. Krook, “A model for collisional processes in gases. I.

small amplitude processes in charged and in nutral one-component systems”, Physical

Review, Vol.94, No. 3, 1954, pp. 511-525.

[9] N.E. Todreas, M.S. Kazimi, Nuclear Systems I-Thermal Hydraulic Fundamentals, Taylor

& Francis, ISBN 1-56032-051-6, 1993

[10] A. N. de Stordeur,"Drag Coefficients for Fuel Element Spacer" Nucleonics, Vol.19, No.6,

1961, pp.746-789.

[11] K. Rehme, "Pressure Drop Correlations for Fuel Element Spacers" Nuclear Technology,

Vol.17, 1973, pp. 15-23.