cfd analysis of turbulent flow phenomena in the lower

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This is a preprint of a paper intended for publication in a journal or proceedings. Since changes may be made before publication, this preprint should not be cited or reproduced without permission of the author. This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party’s use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the United States Government or the sponsoring agency. INL/CON-07-13161 PREPRINT CFD Analysis of Turbulent Flow Phenomena in the Lower Plenum of a Prismatic Gas-Cooled Reactor NURETH-12 T. Gallaway D. P. Guillen H. M. McIlroy, Jr. S. P. Antal M. Z. Podowski September 2007

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Page 1: CFD Analysis of Turbulent Flow Phenomena in the Lower

This is a preprint of a paper intended for publication in a journal or proceedings. Since changes may be made before publication, this preprint should not be cited or reproduced without permission of the author. This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party’s use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the United States Government or the sponsoring agency.

INL/CON-07-13161PREPRINT

CFD Analysis of Turbulent Flow Phenomena in the Lower Plenum of a Prismatic Gas-Cooled Reactor

NURETH-12

T. Gallaway D. P. Guillen H. M. McIlroy, Jr. S. P. Antal M. Z. Podowski

September 2007

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The 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12) Log Number: XXX Sheraton Station Square, Pittsburgh, Pennsylvania, U.S.A. September 30-October 4, 2007.

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CFD ANALYSIS OF TURBULENT FLOW PHENOMENA IN THE LOWER PLENUM OF A PRISMATIC GAS-COOLED REACTOR

T. Gallaway1, D.P. Guillen2, H.M McIlroy2, Jr., S.P. Antal1 and M.Z. Podowski1

(1) Rensselaer Polytechnic Institute, Troy, NY 12180 (2) Idaho National Laboratory, Idaho Falls, Idaho 83406

ABSTRACT

This paper is concerned with the implementation of a computational model of turbulent flow in a section of the lower plenum of Very High Temperature Reactor (VHTR). The proposed model has been encoded in a state-of-the-art CFD code, NPHASE. The results of NPHASE predictions have been compared against the experimental data collected using a scaled model of a sub-region in the lower plenum of a modular, prismatic gas-cooled reactor. It has been shown that the NPHASE-based model is capable of predicting a three-dimensional velocity field in a complex geometrical configuration of VHTR lower plenum. The current and future validations of computational predictions are necessary for design and analysis of new reactor concepts, as well as for safety analysis and licensing calculations.

KEYWORDS: gas-cooled reactor, computational fluid dynamics, particle image velocimetry

1. INTRODUCTION

The Very High Temperature Reactor (VHTR) is part of the proposed Generation IV reactor research. High temperature helium gas will be used as the reactor coolant, giving the reactor, among several benefits, a higher thermal efficiency than currently operating power plants. Presently, reactor designs under consideration include prismatic and pebble bed types. The current project focuses on modeling turbulent flow through the lower plenum of a typical prismatic design used for the General Atomics gas turbine-modular helium reactor (GT-MHR) [MacDonald et al., 2003], shown in Figure 1. Flow is expected to exit the reactor core into the lower plenum at varying temperatures, then mix as it flows around support columns toward the outlet. It is anticipated that the flow conditions will encompass a broad range, from highly turbulent to near stagnant Reynolds numbers throughout the plenum. It is very important for future reactor design considerations and safety analyses that the thermal-hydraulic phenomena governing flow and heat transfer in the VHTR lower plenum be understood in a manner allowing one to accurately predict reactor response to various operating and accident conditions.

The objective of this paper is to present the results of CFD simulations of a section of the GT-MHR prismatic reference design lower plenum using a state-of-the-art computational fluid dynamics (CFD) code, NPHASE [Antal et al., 2000; Tiwari et al., 2006], and to compare the results of NPHASE predictions to experimental data of McIlroy et. al. [2006]. The experimental test section represented a scaled model of a sub-region in the lower plenum, and velocity field measurements were obtained using three-dimensional Particle Image Velocimetry (PIV). The experimental data is part of a validation database that has been used to assess the numerical predictions.

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(a) Isometric view or rector vessel (b) Cross section of lower plenum

Figure 1. GT-MHR reactor design, currently under consideration for the proposed VHTR [MacDonald et al., 2003],

2. EXPERIMENTS

Three-dimensional PIV data was obtained in the Matched-Index-of-Refraction (MIR) Facility at the Idaho National Laboratory (INL) [Condie et al., 2005; McIlroy et al., 2006]. The MIR uses an optical technique, PIV, to obtain non-intrusive flow measurements. The experiments were conducted to study the turbulent flow behavior and to produce data to validate CFD software. The PIV system provides instantaneous and ensemble-averaged velocities at discrete points in the flow.

The model shown in Figure 2 mimics an infinite array of vertical cylindrical support posts arranged on an equilateral triangular pitch. A symmetrical arrangement of five cylindrical columns along the model centerline and ten half-cylinders along the two parallel side walls extend the full height of the model. The columns and inlet jets are 0.03175 m and 0.02210 m in diameter, respectively. The model measures 0.05398 m in width, 0.558 m in length, and 0.21750 m in height. The ratio of the spacing between the post centerlines, L, and the post diameter, D, is L/D=2.94. The relative scale of the model to the full-scale lower plenum section is 1:6.55.

The experiments, although conducted at room temperature, can be directly scaled to the behavior in the prototypical system since at operational conditions the flow is momentum-dominated with negligible buoyancy and nearly constant fluid properties. Scaling studies have been performed to ensure that the flow test model with mineral oil flow under isothermal conditions duplicates the pertinent non-dimensional parameters [McEligot et al., 2004] in the VHTR lower plenum. The model was constructed of quartz, an optically transparent material with the same index of refraction as the mineral oil used as the working fluid of the MIR system. Seeded mineral oil with a precisely controlled temperature of 23.3 ºC enters through four inlet ports above the model. The Reynolds number, based upon jet diameter and bulk flow velocity, is approximately 4300. Mineral oil from the main tunnel flows around the model at a velocity of 0.2 m/s, and mixes with the plenum flow at the model outlet.

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The experiment is designed to simulate the flow in the central portion of the GT-MHR lower plenum, away from the outlet duct. The source of flow entering this region comes from jets exiting short coolant ducts at the corners of the hexagonal blocks, represented in the flow test model as a series of inlet jets located above the plenum. A solid wedge-shaped element at the upstream end simulates the hexagonal support block for the outer reflector and blocks cross flow from the main tunnel flow. The wedge partially blocks the inlet jet at the upstream end.

Figure 2. MIR flow test model.

3. OVERVIEW OF THE NPHASE CODE

The CFD solver used in the present work is the NPHASE code. NPHASE [Antal et al., 2000; Tiwari et al., 2006] is a segregated and coupled, nominally pressure-based finite volume multi-phase/multicomponent CFD code. Individual transport equations are solved for the: momentum, energy and turbulence quantities for each field. Mixture and field continuity equations are solved in coupled or uncoupled fashions, using frozen coefficient linearizations. The code is fully unstructured and can utilize second-order accurate convection and diffusion discretizations. A key feature of NPHASE is that, from the outset, the software design has focused on the development of a reliable solver for multiphase/multicomponent flows. Thus, the various interactions between the individual fields have been incorporated as an inherent part of the solution algorithm. For the current case, the segregated solver is used to resolve an adiabatic, single phase flow field.

The use of unstructured meshes is particularly important for analyzing flows in complex 3-D geometries. Furthermore, hybrid unstructured topologies allow prism or hexahedron elements to be used near solid surfaces for high quality meshes in the boundary layer regions, while accommodating transition to pyramids and tetrahedra in the core flow. The meshes used in the present simulations include hexahedral elements near the wall and prism elements in the core region of the flow.

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In the NPHASE code, the user has a choice of one of three discretization schemes: 1-st order hybrid scheme (default), 1-st order upwind scheme, 2-nd order upwind scheme. For the current simulations, the default scheme is used.

4. COMPUTATIONAL MODEL

4.1. Geometry and Computational Grids

Figure 3 displays the top view of the computational model used to simulate the MIR Facility experimental setup. The four inlet jets are shown, with jet-1 partially blocked by a wedge, as discussed in Section 3. For comparison purposes, four cuts are shown across the z-axis in Figure 3, the first two are labeled 1 and 2. Both the experimental and computational results will be shown at these locations, at two points along the y-axis.

Figure 3. Top view of the geometrical configuration and position of MIR origin used in the NPHASE-based computational model.

The first step in the analysis process is the development of a grid that accurately approximates the flow test model and can adequately resolve important flow features. In order to determine how fine a grid resolution is needed, a grid study was performed with three grids of successively varying mesh refinement. Coarse, medium and fine grids were created to provide a computational mesh for the CFD analysis. The Pointwise software, Gridgen, was utilized in this process to obtain grids representative of the experimental model. Top view sections from each of these grids near the first two inlet jets are shown in Figure 4. For each grid, the node layer nearest the wall was preserved for turbulence modeling purposes. The spacing for this first meshing layer along the wall was set to ~2 mm to produce a y+ 12. This corresponds to the use of standard wall functions in the k- turbulence model in NPHASE. For this reason, a structured grid was created near the walls, and unstructured meshes were created away from the walls wherein the cells are prisms. The coarse grid (shown in Figure 4(a)) contains 322,722 cells; the medium grid (shown in Figure 4(b)) contains 792,534 cells; and the fine grid (shown in Figure

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4(c)) contains 1,346,934 cells. Each of these grids was tested, and the fine mesh was used in the simulations shown in Section 5.

(a) Coarse mesh (b) Medium mesh (c) Fine mesh

Figure 4. Section of the computational grids created for the NPHASE simulations.

In order to accurately model the experimental inlet jets, 9 mm inlet tubes were added to each jet in the computational model. These inlets are shown in a side view of the model in Figure 5 below.

Figure 5. Side view of inlet tube portion of the computational model.

4.2. Governing Equations

Since the current experimental set-up can be modeled as an adiabatic single-phase flow problem, the main component of the NPHASE model is the momentum equation. A conservative form of this equation is given by

Re( )v

vv pt

(1)

where v is the velocity vector, is the viscous shear stress tensor, Re the turbulent ( Reynolds) stress tensor, and the remaining notation is conventional.

As mentioned in Section 2, the turbulent Reynolds number, based on the jet diameter and bulk flow is 4300 and thus a turbulence model is needed to resolve the flow over portions of the geometry. A standard k- turbulence model was chosen to approximate flow in the turbulent regions of the model.

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The corresponding conservation equations for the turbulent energy, k, and energy dissipation, , are as follows

2m

mk

k k ukvt y y y

(2)

2 2

1 2m

muv C C

t y y y k k (3)

where m is the momentum eddy diffusivity and k, , C1, and C2 are dimensionless empirical constants. Typical values for these empirical constants are given below [Bejan, 2004].

C1 = 1.44 C2 = 1.92 k = 1 = 1.3 (4)

4.3. Inlet and Boundary Conditions.

Averaged experimental profiles for velocity components were used as an inlet boundary condition in the computational model for each jet. The turbulent kinetic energy was measured at each of the inlet jets during the experimental analysis. Profiles for this parameter were provided and an averaged inlet turbulent kinetic energy of 0.04 was used as a constant inlet boundary condition. A value of 1.0 was used for the turbulent dissipation. The turbulent dissipation was set based on a comparison between the inlet turbulent and molecular viscosity. These two quantities are expected to be of the same order of magnitude.

5. RESULTS AND DISCUSSION

Typical results of NPHASE simulations, including comparisons against the experimental data for the test facility discussed in Section 2, are presented in this Section.

Each plot shown below displays a component of the velocity for one of the four cross-sections over the z-axis, as shown in Figure 3 and discussed in Section 4.1. The x-axis positions of these cross-sections 3 are 0.12022 m and 0.16850 m, where the former distance corresponds to the location beneath the inlet jet second from the right and the latter refers to the central support post and the inlet jet third from the right. These two positions are labeled in Figure 3 as points 1 and 2, respectively. The y-axis positions chosen for comparison are 0.07 m and 0.15 m from the top of the geometry, and they correspond to approximately one-third and two-thirds, respectively, of the total height of the model.

The first cross-sectional comparison point displayed next falls under the second inlet jet. The dominant velocity at this point is the downward or y-velocity component, as can be noticed by comparing Figures 6, 7, and 8. The magnitude of the x-velocity, in particular at the location closest to the inlet (at y = -0.07 m) shown in Figure 8(a), is relatively low compared to the total velocity magnitude in Figure 6(a). As can be seen in Figure 6(a), the NPHASE prediction is in a good agreement with the experimental result, although the calculated velocity experiences a higher degree of diffusion outside the ±0.01 m distance from the centerline. This excess diffusion of velocity in the computational model may in part be due to the assumed simplified inlet conditions for the turbulent quantities. Due to the lack of any more

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specific information or data, the inlet turbulent energy and dissipation have been set as constant values across the inlet of the flow, whereas in reality the distribution of turbulence is more complex and likely varies across the inlet jets. Thus, the computational model predicts a slightly higher turbulent dissipation of velocity.

x=0.12022 m

0.0000001.0000002.0000003.0000004.000000

-0.03 -0.02 -0.01 0 0.01 0.02 0.03

z (m)

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city

Mag

nitu

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/s)

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z (m)

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Mag

nitu

de (m

/s)

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(b) y = -0.15 m

Figure 6. A comparison between the NPHASE-predicted and measured distribution of the velocity magnitude at Cross-Section-1 (labeled in Figure 3) and x = 0.1202 m.

It is interesting to mention that slight asymmetries have been observed in the flow velocity profiles along the z axis for both the experimental results and the NPHASE predictions, despite the symmetry of the geometric model. These occurred due to the asymmetries in the inlet velocity profiles that have been measured in the experiments, and supplied as input to the NPHASE code.

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x=0.12022 m

-4.000000-3.000000-2.000000-1.0000000.0000001.000000

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z (m)

Y-Ve

loci

ty (m

/s)

y=-0.15m expty=-0.15m NPHASE

(b) y = -0.15 m

Figure 7. A comparison between the NPHASE-predicted and measured distribution of the y-velocity component at Cross-Section-1 (labeled in Figure 3) and x = 0.1202 m.

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x=0.12022 m

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x=0.12022 m

-0.400000-0.2000000.0000000.2000000.4000000.6000000.800000

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z (m)

X-Ve

loci

ty (m

/s)

y=-0.15m expty=-0.15m NPHASE

(b) y = -0.15 m

Figure 8. A comparison between the NPHASE-predicted and measured distribution of the x-velocity component at Cross-Section-1 (labeled in Figure 3) and x = 0.1202 m.

The second cross-sectional slice is located just after a central support post and before the third inlet jet. Here, it is expected that the x-velocity component will only contribute on the outsides of the support post, or ± 0.015 m from the center. A backward flow circulation is also expected between the third inlet jet and the central support post. These phenomena can be seen in Figures 9, 10, and 11. At the y-value farther from the inlet, y = -0.015 m, Figure 10(b) displays a positive y-velocity near the center of the cross section, just behind the support post. This and the corresponding negative x-velocity seen in Figure 11(b) suggest a backward flow circulation which is both seen in experiments and predicted by NPHASE. This circulatory flow can also be observed to a lesser extent at locations closer to the inlet, i.e., at y = -0.07m in Figures 10(a) and 11(a). It can be noticed that the flow near the center of the cross-section appears to be stagnant, while the flow around the support posts displays a slight circulation.

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x=0.16850 m

0.00

0.50

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z (m)

Velo

city

Mag

nitu

de(m

/s)

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(b) y = -0.15 m

Figure 9. A comparison between the NPHASE-predicted and measured distribution of the velocity magnitude at Cross-Section-2 (labeled in Figure 3) and x = 0.1685 m.

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x=0.16850 m

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z (m)

Y-Ve

loci

ty (m

/s)

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(b) y = -0.15 m

Figure 10. A comparison between the NPHASE-predicted and measured distribution of the y-velocity component at cross-section-2 (labeled in Figure 3) and x = 0.1685 m.

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x=0.16850 m

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ty (m

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z (m)

X-Ve

loci

ty (m

/s)

y=-0.15m expty=-0.15m NPHASE

(b) y = -0.15 m

Figure 11. A comparison between the NPHASE-predicted and measured distribution of the x-velocity component at cross-section-2 (labeled in Figure 3) and x = 0.1685 m.

As can be noticed, the major trends observed in the experimental results at the second comparison point appear to be nearly replicated by the computational results from NPHASE.

The predicted contour plots for the relative pressure and the magnitude of the velocity are shown in Figures 12 and 13. These contours have been taken along the x-axis. Hence, there is a gap in the flow results for each central support post but not for the side support posts. The circulation underneath the third and fourth jets can be observed in Figure 12. This phenomenon was also observed in Figures 10 and 11.

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Figure 12. Velocity magnitude contour plots.

Figure 13. Pressure contour plots.

6. CONCLUSIONS

The results of complete three-dimensional CFD simulations have been presented of fluid flow in the complex geometry of a scaled model of the lower plenum of a proposed prismatic gas-cooled reactor. The computations have been performed using the NPHASE computer code. It has been shown that the current numerical solver is both robust and accurate. The results of NPHASE predictions have been compared against the experimental taken using a simulant fluid. Given the various uncertainties of the measurements, one concludes that the NPHASE-based model properly predicted the dominant fluid mechanics phenomena governing flow distribution and velocity field in the complex geometry of the modeled section of the VHTR lower plenum. Whereas the current results are very promising, more work is clearly needed in order to improve the accuracy of predictions over a large range of the anticipated reactor operating conditions and postulated accident situations.

ACKNOWLEDGMENTS

This manuscript has been authored by Battelle Energy Alliance, LLC under Contract No. DE-AC07-05ID14517 with the U.S. Department of Energy. References herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government, any agency thereof, or any company affiliated with Idaho National Laboratory.

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REFERENCES

S.P. Antal, S.M. Ettorre, R.F. Kunz and M.Z. Podowski, M. Z., “Development of a Next Generation Computer Code for the Prediction of Multicomponent Multiphase Flows”, Proc. Int. Meeting on Trends in Numerical and Physical Modeling for Industrial Multiphase Flow, Cargese, France (2000).

A. Bejan, Convection Heat Transfer, John Wiley & Sons, Hoboken, New Jersey (2004).

K.G. Condie, G.E. McCreery, H.M. McIlroy, Jr., D.M. McEligot, “Development of an Experiment for Measuring Flow Phenomena Occurring in a Lower Plenum for VHTR CFD Assessment”, Tech. report INL/EXT-05-00603, INL (2005).

P.E. MacDonald, J.W. Sterbentz, R.L. Sant, P.D. Bayless, R.R. Schults, H.D. Gougar, R.L. Moore, A.M. Ougouag and W.K. Terry, “NGNP preliminary Point Design – Results of the initial neutronics and thermal-hydraulic assessments”, Tech. Report INEEL/EXT-03-00870 Rev. 1, INEEL (2003).

D.M. McEligot and G. E. McCreery, “Scaling studies and conceptual experiment designs for NGNP CFD assessment”, Tech. Report INEEL/EXT-04-02502 (2004).

H.M. McIlroy et al., “PIV Experiments of Measure Flow Phenomena in a Scaled Model of a VHTR Lower Plenum”, Idaho National Laboratory Report INL/INT-06-11740, September (2006).

P. Tiwari, S.P. Antal and M.Z. Podowski, "Three-Dimensional Fluid Mechanics of Particulate Two-Phase Flows in U-bend and Helical Conduits", Physics of Fluids, 18, 4, pp.1-18 (2006).