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Science and Technology of Nuclear Installations

Volume 2011 (2011), Article ID 941239, 10 pages

http://dx.doi.org/10.1155/2011/941239

## CFD Modeling of Wall Steam Condensation: Two-Phase Flow Approach versus Homogeneous Flow Approach

^{1}Electricité de France R&D Division, 6 Quai Watier, 78400 Chatou Cedex, France^{2}INCKA, 85, Avenue Pierre Grenier, 92100 Boulogne Billancourt, France

Received 14 March 2011; Revised 3 May 2011; Accepted 6 May 2011

Academic Editor: Giorgio Galassi

Copyright © 2011 S. Mimouni et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

#### Abstract

The present work is focused on the condensation heat transfer that plays a dominant role in many accident scenarios postulated to occur in the containment of nuclear reactors. The study compares a general multiphase approach implemented in NEPTUNE_CFD with a homogeneous model, of widespread use for engineering studies, implemented in *Code_Saturne*. The model implemented in NEPTUNE_CFD assumes that liquid droplets form along the wall within nucleation sites. Vapor condensation on droplets makes them grow. Once the droplet diameter reaches a critical value, gravitational forces compensate surface tension force and then droplets slide over the wall and form a liquid film. This approach allows taking into account simultaneously the mechanical drift between the droplet and the gas, the heat and mass transfer on droplets in the core of the flow and the condensation/evaporation phenomena on the walls. As concern the homogeneous approach, the motion of the liquid film due to the gravitational forces is neglected, as well as the volume occupied by the liquid. Both condensation models and compressible procedures are validated and compared to experimental data provided by the TOSQAN ISP47 experiment (IRSN Saclay). Computational results compare favorably with experimental data, particularly for the Helium and steam volume fractions.

#### 1. Introduction

Condensation heat transfer in the presence of noncondensable gases is a relevant phenomenon in many industrial applications, including nuclear reactors.

In particular, during the course of a hypothetical severe accident in a nuclear pressurized water reactor (PWR), hydrogen may be produced by the reactor core oxidation and distributed into the reactor containment according to convective flows, water steam wall condensation, and interaction with the spraying droplets. In order to assess the risk of detonation generated by a high local hydrogen concentration, hydrogen distribution in the containment vessel has to be known. The TOSQAN experimental programme [1] has been created to simulate typical accidental thermal hydraulic flow conditions of the reactor containment. The heat and mass exchanges between the spray droplets and the gas with thermal hydraulic conditions representative of this hypothetical severe accident have been studied in [2]. The aim of this work is, thus, to focus on wall condensation.

To evaluate the condensation modelling of containment codes, ISP47 test was performed in the TOSQAN facility (OECD). The TOSQAN facility is a large enclosure devoted to simulate typical accidental thermal hydraulic flow conditions in PWR containment (Section 4). It is highly instrumented with nonintrusive optical diagnostics. Therefore, it is particularly suitable for nuclear safety CFD code validation.

This issue has already been addressed by using computational fluid dynamics (CFD) codes as CFX code [3]. In these calculations, the flow is modelled as a single-phase and the condensation acts as a sink of mass and energy. In this approach, the liquid film and the influence of the noncondensable gas layer are reduced to a simple sink term. On the other hand, the use of explicit correlations to evaluate heat and mass transfer processes, though it represents a feasible approach for large experimental facilities and reactor plant containments, partly ignores the useful information provided by the detailed CFD models in relation to local conditions.

Another modelling is proposed in [4] with the FLUENT code. With this approach, heat and mass correlations are replaced by using “fundamental” physical laws. But, in that case, a very fine computational grid is required; the adopted two-dimensional grid discretizes the vessel gas region of TOSQAN experiment in about 28500 cells (average size of 1 cm) instead of 4800 for the former case (average size of 2.6 cm).

The main objective of the paper is to propose a novel condensation model based on “fundamental” physical laws without requiring a very fine computational grid; 7500 cells are used for TOSQAN ISP47 test, and the grid is uniform. In reactor applications, droplets at the wall come from vapor condensation or sprays. The computation of heat and mass transfer between a spray and a gas mixture has already been addressed [2].

In fact, thanks to a code-to-experiment benchmark based on 2 tests of the TOSQAN facility [5], we successfully evaluated the ability of the code to reproduce the droplet heat and mass transfer on one hand (TOSQAN 101 case) and the gas entrainment and atmosphere mixing by the spray on the other hand (TOSQAN 113 case). A novel model dedicated to the droplet evaporation at the wall was also proposed [2]. As a consequence, the vapor condensation model can be seen as an extension of the previous model.

Moreover, it is of primary importance to take into account both evaporation and condensation phenomena. In fact, Andreani et al. [6] underline that depending on the break location and the geometry of the containment, liquid films could flow into dry regions where the liquid would evaporate. If walls are hotter than the liquid film, this would result in an enhanced evaporation rate. The two-phase flow approach adopted in the paper allows taking into account simultaneously the mechanical drift between the droplet and the gas, the heat and mass transfer on droplets in the core of the flow, and the condensation/evaporation phenomena on the walls. But, the calculations of the wall condensation with a homogeneous model (as implemented in Code_Saturne) (Archambeau, 2004), of widespread use for engineering studies, give also reasonable results; as a consequence, the comparison between these two methods allows to underline their advantages and drawbacks, respectively.

The paper is organized as follows. First, we describe briefly the set of equations solved in the NEPTUNE_CFD and Code_Saturne codes. In the last part, the two-phase flow model and the homogenous models are compared and validated by simulating the TOSQAN ISP47 test on global and local variables. Both models have been already validated against COPAIN test [7].

#### 2. The Numerical Solver and Physical Modeling: NEPTUNE_CFD Code

The solver belongs to the well-known class of pressure-based methods. It is able to simulate multicomponent multiphase flows by solving a set of three balance equations for each field (fluid component and/or phase) [8, 9]. These fields can represent many kinds of multiphase flows: distinct physical components (e.g., gas, liquid, and solid particles), thermodynamic phases of the same component (e.g., liquid water and its vapour), distinct physical components, some of which split into different groups (e.g., water and several groups of different diameter bubbles), and different forms of the same physical components (e.g., a continuous liquid field, a dispersed liquid field, a continuous vapour field, a dispersed vapour field). The solver is implemented in the NEPTUNE software environment [10, 11], which is based on a finite volume discretization, together with a collocated arrangement for all variables. The data structure is totally face based which allows the use of arbitrary shaped cells (tetraedra, hexaedra, prisms, pyramids, …) including nonconformal meshes.

The main interest of the numerical method is the so-called “volume fraction-pressure-energy cycle” that ensures mass and energy conservation and allows strong interface source term coupling [12].

Mass balance equations, momentum balance equations, and total enthalpy balance equations are solved for each phase. The gas turbulence is taken into account by the classical k-*ε* model. The droplet diameter evolution is calculated from an equation of transport on the density of drops. Additional equations are added to take into account the noncondensable gases (air and helium). As concerns the interfacial momentum transfer terms, the only force exerted on droplet is the drag force. Small droplets stick at the wall and large drop slide along the wall under the competition between the surface tension and the gravity force. As a consequence, the gas velocity near the wall does not tend to zero but to the droplets velocity because of the drag force. This is a major difference between single-phase and two-phase flow approach [7]. As concerns the heat and mass transfer between droplets and the wall, it is based on the balance of heat and mass transfer between a drop and the gas mixture surrounding the drop using the correlations of Ranz and Marshall [13] which are of widespread use.

The model of drop-wall interaction which was developed and implemented is written as a symmetric extension of the nucleate boiling model at the wall and uses as a starting point the model of mass transfer in the core flow. To establish this model, we made the following assumptions:the drops which accumulate on the walls take a hemispherical form;there is no nucleate boiling inside the drops at the wall;the drops which impact the walls successively see a stage of cooling (resp., heating) and a stage of condensation (resp., evaporation);the droplets stick to the wall (no rebound), or slide along the wall.

The total heat flux exchanged between the wall and the flow is split into four terms: a single-phase flow convective heat flux at the fraction of the wall area unaffected by the presence of droplets (heat transfer between the gas and the wall); a single-phase flow convective heat flux at the fraction of the wall area affected by the presence of a liquid film (heat transfer between the liquid film and the wall); a single-phase flow heat flux to decrease (resp., increase) the droplet temperature and reach the wall temperature (resp., the saturation state) (heat transfer between the droplets and the wall); a condensation (resp., vaporisation) heat flux.

Details can be found in [2]. An extensive validation process has been achieved in [7] against the COPAIN experiment, and mesh sensitivity has been found acceptable.

#### 3. Homogeneous Gas Dynamic Model Used in Code_Saturne

The motion of gases and heat transfer in containment enclosures can be described by the general momentum, partial masses, and energy conservation equations.

The predominant physical phenomena driving the distribution and heat transfer of fluids within containment enclosures are the following.Mixing and/or segregation of gas whose velocity, density, and temperature are different.“Swelling” of containment: the compressibility of gas is taken into account, even if the flow velocities are low.Laminar and controlled combustion of hydrogen in recombiners, in order to limit the concentration of this gas.Condensation of steam on cold structure surfaces, which has the main effect of limiting the pressure rise.

The general momentum, partial masses, and energy conservation equations describing these phenomena can be simplified, and stiffness due to the presence of physics having very different characteristic length and time scales can be removed or relaxed.

Steam condensation on the walls of the containment enclosure plays a key role in the dynamic and heat transfer. The heat and mass sink terms of gases due to condensation are modeled through correlations based on heat and mass transfer analogy of Chilton-Colburn type. The liquid film is not modeled, and it is assumed that vapor and noncondensable gases are in direct contact with the wall. The modelling of the heat transfer by condensation of steam in liquid can be found in [14].

#### 4. TOSQAN ISP47 Test

##### 4.1. TOSQAN Experiments

The TOSQAN experiment (Figure 1) is a closed cylindrical vessel (7 m^{3}, i.d. 1.5 m, total height of 4.8 m, and condensing height of 2 m) into which steam or noncondensable gases are injected through a vertical pipe located on the vessel axis. This vessel has thermostatically controlled walls so that steam condensation may occur on one part of the wall (the condensing wall), the other part being superheated (the noncondensing wall). The entire transient of the ISP47 test lasted about 18000 s. During certain phases of the experiment, steady states were reached when the steam condensation rate became equal to the steam injection rate, while all boundary conditions (in particular, wall temperatures and steam injection rates) were kept constant. The boundary conditions during different steady states were different. The boundary conditions are summed up in Table 1 [1].

##### 4.2. Numerical Setup

The initial conditions for the thermo-fluid-dynamic variables necessary to start the simulation of the transient were evaluated through a preliminary calculation, with no mass flow rate at the inlet section and with only air present inside the vessel.

The mean upper (resp., lower) noncondensing wall temperature is maintained constant and equal to 122.0°C ±1 (resp., 123.5°C ±1) during the whole test.

Gas temperature, volume fractions, and gas velocity measurements are available on TOSQAN at different heights . The flow is assumed to be axisymmetric so that a two-dimensional axisymmetric mesh is used. Two-dimensional representations of axial velocity and gas temperature with NEPTUNE_CFD are illustrated on Figure 2. Computations with NEPTUNE_CFD have been performed on two kinds of meshing: a grid with 7500 cells (average size of 2 cm) and a fine grid with 32000 cells (average size of 1 cm). Results are similar (Figure 5) between “standard” (7500 cells) and fine mesh (32000 cells). Hence, the subsequent computations with NEPTUNE_CFD are performed on the “standard” grid (7500 cells). Calculations performed with Code_Saturne use about 1700 cells. The cells are of hexahedral shape.

##### 4.3. Results and Discussion

In this section, experimental values are compared to the values calculated with the NEPTUNE_CFD code with a two-phase flow approach. In some figures, values calculated with Code_Saturne (homogenous approach) have been added and named “saturne”.

The evolution of the relative pressure during the whole transient is illustrated by Figure 3 and compares quite favourably with experimental data. This figure gives a general idea of the successive stages.

###### 4.3.1. Gas Temperature Profiles

The gas temperature compares favourably with experimental results in the lower part of the TOSQAN vessel but is overestimated in the upper part in plume or jet-plume configuration (Figures 8, 9, 14, and 16). In jet configuration, the gas temperature profiles are in reasonable agreement with the experimental data, including near the wall (Figures 10 and 11). We recall that a plume is a column of one gas moving through another. Several effects control the motion of the fluid, including momentum, diffusion, and buoyancy (for density-driven flows). When momentum effects are more important than density differences and buoyancy effects, the plume is usually described as a jet.

###### 4.3.2. Gas Velocity Profiles

The gas temperature results are correlated to the gas velocity that is correctly predicted in the steady state 2 (Figure 13) whereas discrepancies are observed for the steady state 1 (Figure 4).

Steam mean mass flow rate at steady state 1 is 1.11 g/s. At the injection mean temperature, namely, 126°C, the vapor density is kg/m^{3}. The internal diameter of the injection tube is mm.

We deduce the vapor velocity at outlet ( m) of the injection tube by which leads to m/s. This value is coherent with the radial profile of the axial velocity at m where a peak along the axis is observed (Figure 4). If we assume that condensation may occur in the core flow, then droplets may form (wet vapor). Because of the mass flow rate conservation, the gas velocity at injection is lower, and the comparison calculated/experimental values is improved for the velocity profiles. But, with condensation in the core flow, calculations show that the gas temperature is globally overestimated in the vessel. As a consequence, more investigations are still needed to check if the mass transfer in the core flow can be neglected. Particularly, the heat and mass transfer in the core flow strongly depends on the droplets diameter for which the initial values are crucial.

Another reason could explain the discrepancies about the vertical gas velocity, the modelling of turbulence in buoyant jet configuration, since the empirical constants of the turbulence models are fitted to jet configurations. In fact, the axial gas velocity profile is in reasonable agreement with the experimental data for the steady state 2 (Figure 13). But, the axial gas velocity profiles (Figure 15) for the steady state 3 and 4 (plume jet configuration like the steady state 1) are also in reasonable agreement with the experimental data; hence, discrepancies are not only due to the turbulence modelling.

###### 4.3.3. Helium and Vapor Volume Fraction

Vapor volume fraction globally compares favourably with the experimental results (Figures 6, 7, 12, 17, and 18). Hence, the two-phase flow approach proposed to predict vapor condensation on a cooled surface in the TOSQAN ISP47 test is successfully validated in terms of condensation flux whereas discrepancies remain for the heat flux between the wall and the gas mixture in plume configurations. However, these discrepancies should have no impact on safety considerations according to [1].

Moreover, in the homogenous approach (cheap in computational time), the liquid film is not modeled and it is assumed that vapor and noncondensable gases are in direct contact with the wall. Thus, the gas velocity tends to zero at the wall. In the two-phase approach (expensive in computational time), vapor condensates at wall and forms a liquid film. Thus, the gas velocity tends to the liquid film velocity near the wall. As a consequence, the stratification calculated with the two-phase flow approach is accurately calculated in Figure 18 whereas discrepancies are observed with the homogeneous approach.

As a consequence, the helium volume fraction profiles are in good agreement with the experimental data (Figures 17 and 18) because the mixture density equals the sum of vapour, air, and helium density. Nevertheless, the accuracy prediction of the global condensate liquid is only a necessary condition. In fact, at s, the helium injection is stopped, and, hence, the mass of helium is constant in the vessel. In most of numerical CFD codes, the helium mass balance equation is usually solved after the mass, momentum and energy balance equations which leads to a numerical error on the helium mass conservation. This numerical error can be neglected for short physical times but can exceed 20% for long transient calculations. Therefore, in a word, the noncondensable gases (air and helium) mass balance equations are solved inside the so-called “volume fraction-pressure-energy cycle” that ensures mass conservation.

These results are relevant for safety considerations, given that in applications, hydrogen (explosive gas) is produced in nuclear power plan containment at accident conditions instead of helium.

NEPTUNE_CFD results and *Code_Saturne* results are in good agreement globally.

#### 5. Conclusion

A large amount of steam and hydrogen gas is expected to be released within the dry containment of a pressurized water reactor (PWR), after the hypothetical beginning of a severe accident leading to the melting of the core. The accurate modeling of gas distribution in a PWR containment concerns phenomena such as wall condensation, hydrogen accumulation, gas stratification, and transport in the different compartments of the containment. The paper presents numerical assessments of CFD solvers NEPTUNE_CFD and *Code_Saturne* and is focused on the analysis and the understanding of gas stratification and transport phenomena.

We have presented in this paper the wall condensation modelling implemented in NEPTUNE_CFD, a three dimensional two-fluid code dedicated to nuclear reactor applications. A novel model dedicated to the droplet evaporation at the wall was proposed in [2] and generalized in this work to the vapor condensation on a cooled surface.

Thanks to a code-to-experiment benchmark based on the COPAIN facility, we successfully evaluated the ability of the codes to reproduce the vapor condensation at wall in a previous work [7]. In this paper, both codes are validated and compared with experimental data corresponding to the TOSQAN ISP47 test. The obtained computational results compare fairly well with experimental data and other computational results obtained with others codes as CFX [3] and FLUENT [4] codes.

Moreover, during the course of a severe accident in a pressurized water reactor (PWR), spray systems are used in containment in order to limit overpressure, to enhance the gas mixing in case of the presence of hydrogen, and to drive down the fission products. Hence, vapor condensation on a cooled surface and spray systems act simultaneously during the course of a severe accident. The two-phase flow approach proposed in the paper allows to simulate both phenomena simultaneously.

Predictions regarding axial velocity do not agree in some cases because of turbulence modelling. One alternative in further studies might be to use reynolds stress transport model to deal with turbulence modelling (Mimouni and Archambeau, 2010), [15]. Future work will also concern mesh sensitivity studies comprising structured mesh (hexahedra) or unstructured mesh (tetrahedron).

#### Acknowledgments

This work has been achieved in the framework of the PAGODES2 project financially supported by EDF (Electricité de France). The NEPTUNE_CFD code is being developed in the framework of the NEPTUNE project financially supported by CEA (Commissariat à l’Energie Atomique), EDF (Electricité de France), IRSN (Institut de Radioprotection et de Sûreté Nucléaire), and AREVA-NP.

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