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Numerical Investigation on Boiling Channel Instabilities by Imposing Constant Pressure Drop Boundary Condition via a Large Bypass

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Numerical Investigation on Boiling Channel Instabilities by Imposing Constant Pressure Drop Boundary Condition via a Large

Bypass

Marco Colombo, Antonio Cammi, Davide Papini, Marco Ricotti Politecnico di Milano – Department of Energy

CeSNEF – Nuclear Engineering Division Via La Masa, 34 – 20156 Milano, Italy

marco3.colombo@mail.polimi.it

ABSTRACT

Density Wave Oscillations (DWOs) are probably the most common type of instabilities affecting vapor generation in boiling systems. They are “dynamic type” instabilities, which result from multiple feedback effects between the flow rate, the vapor generation rate and the pressure drops in the boiling channel. Several experimental studies on density wave instabilities have been reported in the open literature since the 60s-70s, due to the great importance that instability concern has for the operation and safety of various industrial applications, including steam generators and boiling water nuclear reactor cores.

A constant pressure drop is the proper boundary condition which can excite the fundamental mechanisms leading to the appearance of DWOs in a single channel. Therefore, several experimental works were conducted using a large bypass pipe, to impose the mentioned boundary condition on the boiling channel. As a matter of fact, the mass flow rate is generally forced in an experimental apparatus by a feedwater pump, instead of being driven by a pressure difference imposed across the channel. A large bypass tube is hence necessary to maintain the constant pressure drop condition on the single heated channel.

In this framework, the described experimental layout is investigated by means of the RELAP5/MOD3.3 code: a single heated pipe is connected to a large bypass by means of two branches, which also permit to account for local pressure losses. The simulation data are clustered in dimensionless stability maps, generally adopted in such stability investigations.

The influence on stability of the bypass ratio is also investigated.

The results aim to be a contribution to the assessment of the code capability to detect the onset of two-phase flow instabilities in a boiling channel. Within this respect, the code could provide a useful background for an experimental campaign focused on a single boiling channel.

1 INTRODUCTION

Two-phase flow instabilities have been widely studied in the past because they are of interest to the design and operation of many industrial systems, such as boiling water reactors or steam generators. The various types of self-sustained oscillations which could arise in a boiling channel have been reviewed and classified in different literature works [1],[2].

Amongst them, Density Wave Oscillations (DWOs) are probably the most common, and they

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are related to multiple dynamic feedback effects between the flow rate, the vapor generation rate and the pressure drops in the boiling channel.

A description of the physical mechanism leading to the appearance of DWOs is provided by Yadigaroglu and Bergles [3], with respect to a single heated channel with an imposed total pressure drop. The channel is divided into a single-phase region and a two- phase region by the boiling boundary, which is the point where the fluid reaches the saturation temperature. An instantaneous perturbation of the flow rate causes an enthalpy perturbation propagating through the channel, which affects both the boiling boundary position and the length of the two different regions. The result is a perturbation in the single-phase pressure drop - δΔp1 - and a two-phase pressure drop perturbation of the opposite sign - δΔp2 -. If the total pressure drop vanishes, the system is found to be on the threshold of stability for a set of operating conditions and for a given inlet flow perturbation:

2 0

1+ Δ =

Δ

=

Δp δ p δ p

δ (1)

The difference in density between the subcooled liquid entering the heated channel and the low density two-phase mixture exiting triggers delay in the transient distribution of pressure drops along the duct which may lead to self-sustained oscillations. These oscillations are characterized by waves of heavier and lighter fluid propagating towards the exit section.

Since a cycle is completed by the passage of two perturbations, the period of oscillations should be of the order of twice the transit time of the mixture.

In recent years, Rizwan-Uddin [4] and Podowski [5] proposed different descriptions based on more complex relations between the system parameters. Their explanation is based on the different speeds of propagation of velocity perturbations between the single-phase region (speed of sound) and the two-phase region (so named kinematic velocity). This behavior is dominant at high inlet subcooling, such that the phenomenon seems to be governed more likely by flow oscillations rather than by density waves propagation. In this case, the period of oscillations is larger than twice the mixture transit time.

Ambrosini et al. [6] observed that both flow perturbations and density waves superimpose and interact during boiling channel oscillations, resulting in a very complex behavior. The Authors investigated the subject using a simple homogeneous equilibrium model, discretized with a semi-implicit numerical method. The adoption of simplified analytical models is well established to study basic thermalhydraulic phenomena;

nevertheless, the use of complex numerical system codes represents a reliable option, since they can provide accurate quantitative predictions with simple and straightforward nodalizations. Ambrosini and Ferreri [7] performed a detailed analysis about thermalhydraulic instabilities in a boiling channel using both a simplified single channel model and the RELAP5/MOD3.2 code. They investigated a single channel layout with imposed pressures kept constant by two inlet and outlet plena, demonstrating the capability of the RELAP5 system code to detect the onset of DWO instability.

Objective of the present work is to assess the behavior of the RELAP5 code simulating a different system configuration, in which a large bypass is used to impose the constant pressure drop boundary condition on the boiling channel. The bypass solution is typically adopted experimentally to impose the constant pressure drop condition on the single heated channel [8]. As a matter of fact, the mass flow rate is forced by an external feedwater pump instead of being driven by the pressure difference across the channel. The investigated layout is thus representative of a typical experimental setup. In this framework, the code could provide a valuable pre-test analysis tool in preparation of experimental campaigns on single channel instabilities. Besides the capability of the code to detect the onset of instability with the selected configuration, the bypass ratio required to maintain the pressure boundary

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condition and the effect on stability of the value of such ratio are also investigated. Section 2 describes the RELAP 5 nodalization and the numerical setting adopted, whereas in Section 3 simulation results and the sensitivity analysis are presented.

2 RELAP5 MODEL AND NUMERICAL SETTING

A typical experimental setup adopted to study DWOs in a single boiling channel is depicted in Figure 1. A large bypass tube is connected to the heated test channel. Such configuration guarantees a constant pressure drop across the channel, which is the proper boundary condition to excite the dynamic feedbacks being at the source of the instability mechanism.

The layout is modeled with the RELAP5/MOD3.3 code [9] connecting two pipe components of different diameter by means of two branches (Figure 2-a). The mass flow rate is provided by a time-dependent junction, connected directly to the lower branch. Inlet pressure and temperature are fixed using a time-dependent volume. Outlet pressure is imposed by another time-dependent volume connected to the upper branch by means of a single junction. Local pressure loss coefficients kin and kout are introduced on the four connections between branches and pipe components, and simulate the presence of inlet and exit throttling. Pressure drop across the channel is imposed by the exit pressure, the mass flow rate and the characteristic of the channel. The heated channel is subdivided in 48 nodes and features dimensions and operating pressures which correspond to the values of a classical BWR subchannel (Table 1). In details, the geometric parameters and the number of nodes are derived from [7], to make easier a comparison of simulation results. The number of nodes is also selected following other remarks which will be discussed later. Imposed heat flux condition is adopted. The heat structures wherein power generation is accounted are assumed very thin and present high thermal conductivity and low heat capacity to avoid distortions in the imposed thermal flux condition, and to neglect tube wall dynamic behavior as well. As far as the bypass ratio (Rby=Aby/Ahc) is concerned, the initial value of the bypass diameter is assumed equal to 10 times the diameter of the heated channel (Rby=100), in order to ensure the constant pressure drop boundary condition.

The following procedure is adopted to reach the instability boundary for the different operating conditions: at the beginning of each run specific values of exit pressure, mass flow rate and inlet water temperature are selected as initial conditions. Flow circulation in the system starts at zero power, then power generation in the heat structures is increased gradually till the unstable condition is reached. The increase rate is higher at the beginning of the transient, to quickly approach the unstable region, then it is lowered to guarantee an easier detection of the onset of instability.

   

Storage Tank Pump Throttling Valve Preheater

Pressure Control Valve

BYPASS

TEST SECTION (Heated Channel)

Table 1 RELAP5 simulation parameters.

Heated Channel

Diameter [m] 0.0124

Length [m] 3.658

Roughness [m] 2.5·10-5 Operating parameters

Exit pressure [Pa] 7.0·106 Inlet temperatures [°C] 151.3 - 282.3

kin 23

kout 5

Figure 1 Typical experimental layout

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  b)

Heated Channel

Time-dependent Volume

Time-dependent Volume

Heat Structure a)

Lower Branch Time-dependent

Volume Time-dependent

Junction Bypass Heated

Channel

Heat Structure

Single Junction

Upper Branch Time-dependent

Volume

Figure 2 RELAP5 nodalization in the two different configurations: a) with a bypass tube;

b) with a single channel alone.

Collected data are clustered into useful stability maps, which permit to easily identify the stable and unstable regions. Most used dimensionless stability maps were introduced by Ishii and Zuber [10] using a phase change number Npch and a subcooling number Nsub, defined as follows:

l lv lv

in sub l

lv lv

pch v

v h N h

v v h

N q Δ ⋅

=

⋅ ⋅

= Γ (2)

The two numbers permit to represent in a 2-D space the instability boundary as function of inlet subcooling, mass flow rate and thermal power for fixed values of system pressure and inlet and exit throttling.

Ambrosini and Ferreri [7] investigated in details the predictive capabilities of the RELAP5 code, when used to simulate the appearance of DWOs in a single boiling channel (Figure 2-b). The Authors performed a large number of calculations to analyze the effect on the results of the different models available in the code, as well as the nodalization and the numerical scheme. Their results are considered the starting point for the present analysis, in which the same models and numerical settings are adopted.

The UVUT (Unequal Velocities Unequal Temperatures) model is adopted, because it is found to be more robust and reliable when compared with the EVET (Equal Velocities Equal Temperatures) model, which is indeed more conservative [7]. The semi-implicit numerical scheme is selected. Calculations rarely crash due to numerical problems, and the introduction of numerical diffusion is limited with respect to the nearly-implicit numerical scheme [7]. To reduce as much as possible the amount of numerical diffusion introduced also with the semi- implicit discretization, a control variable which forces the time step to remain equal to a fixed value of the Courant number has been developed:

tCou

t= ⋅Δ

Δ 0.95 (3)

Finally, a number of nodes equal to 48 is selected as in [7]. Smoother prediction of the stability boundary is assured also in the case of the UVUT model, even though it is less sensitive to variations of the number of nodes.

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3 RESULTS

The first set of data were collected adopting a bypass ratio Rby=100 and exploring different inlet temperatures. Figure 3 shows a comparison between the maps obtained with the bypass tube and with the single heated channel.

0 1 2 3 4 5 6 7 8 9

0.0 5.0 10.0 15.0 20.0 25.0 30.0

Nsub

Npch

Single Channel Bypass

Figure 3 Stability map calculated with the bypass tube (Rby=100) compared with the stability map obtained in a single channel with imposed pressure drop.

The pressure drop across the heated channel was taken equal in the two different scenarios. The presence of a large bypass tube does not influence the onset of instability and only small deviations are observed at very low subcooling numbers.

It is important to notice that the criterion to detect the appearance of DWOs is not an exact one, thus it is expected to affect the results introducing some uncertainty. The stability boundary has been detected by the appearance of growing oscillations in the mass flow rate through the heated channel (Figure 4). The system was considered unstable when the oscillations appeared fully developed.

Figure 4 Mass flow rate behavior in the heated channel during a simulation performed with Nsub=4.

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In accordance with literature results [1], the effect of the inlet subcooling on system stability is found to be stabilizing at high subcoolings and destabilizing at low subcoolings.

The results of the single channel alone simulations show also a fair agreement with the ones obtained in [7].

The period of oscillations, which is known from literature to grow with the subcooling number, is correctly reproduced by the RELAP5 code with the bypass configuration, as it is shown in Figure 5. It was calculated by the code with a dedicated control variable as the ratio between mass and mass flow rate in the heated channel. The ratio between the period of oscillations and the transit time in the two configurations (single channel alone and with the bypass) is depicted. As expected, this ratio increases with higher inlet subcoolings [7].

0.0 0.5 1.0 1.5 2.0 2.5 3.0

0 2 4 6 8

T/t

N

sub

Single Channel Bypass

Figure 5 Ratio between the period of oscillations and the transit time in the heated channel with and without the bypass tube.

3.1 Sensitivity analysis

The influence of the bypass area on system stability has been investigated performing a sensitivity analysis on the bypass ratio. Bypass ratio was at first reduced to find out the value required to guarantee a constant pressure drop across the heated channel. The results are presented in Figure 6.

Halving the bypass ratio (Rby=50) does not modify the stability of the heated channel.

On the contrary, further reduction tends to render the system more stable (stability curves shifted to the right in the Npch-Nsub space).

Stable region becomes larger when the bypass ratio is reduced to 20, except for low inlet subcoolings, for which the stability boundary is rather unchanged. A last reduction to 10 remarkably widens the stability region. Hence, a bypass ratio at least equal to 20 is needed to maintain properly the constant pressure drop boundary condition.

Increasing the bypass ratio (up to 200 and 500 respectively) does not affect significantly the stability of the system. As it is shown in Figure 7, the stability is independent on the bypass ratio for sufficiently large values.

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0 1 2 3 4 5 6 7 8 9

0.0 5.0 10.0 15.0 20.0 25.0 30.0

Nsub

N

pch

10 20 50 100

Figure 6 Stability maps obtained with different values of the bypass ratio Rby (respectively 100, 50, 20 and 10).

0 1 2 3 4 5 6 7 8 9

0.0 5.0 10.0 15.0 20.0 25.0 30.0

Nsub

N

pch

500 200 100

Figure 7 Stability maps obtained with different values of the bypass ratio Rby (respectively 100, 200 and 500).

4 CONCLUSIONS

Capability of the RELAP5 system code to detect the appearance of density wave oscillations in a single boiling channel was studied. Investigated configuration includes a large bypass tube to impose a constant pressure drop boundary condition on the boiling channel, which is the proper boundary condition to excite the instability mechanism. As a matter of fact, a large bypass is typically used to impose the mentioned boundary condition during experimental investigations about single boiling channel instability.

The RELAP5 code demonstrated its capability to correctly detect the onset of instability. A sufficiently large bypass permits to reproduce the same results obtained with

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single channel alone simulations. Only small deviations were detected at low inlet subcoolings.

A sensitivity analysis has been performed on the bypass ratio. Lower values of the bypass ratio (20 and 10) induced a significant stabilization of the system. On the other hand, system stability was found to be independent on the bypass ratio for sufficiently high values of the bypass area.

The present work aims to be a contribution to the assessment of the RELAP5 code capability to properly detect and reproduce DWOs phenomena in a single boiling channel.

ACKNOWLEDGMENTS

The Authors are grateful to professor Walter Ambrosini (University of Pisa) for the initial technical support and useful suggestions on the code numerical setting.

NOMENCLATURE Aby bypass area [m2]

Ahc heated channel area [m2] h enthalpy [J/kg]

k valve loss coefficient Npch phase change number Nsub subcooling number p pressure [Pa]

q thermal power [W]

Rby bypass ratio

T period [s]

t transit time [s]

Δt time step [s]

v specific volume [m3/kg]

Г mass flow rate [kg/s]

Subscripts

Cou Courant

l liquid

v vapor

REFERENCES

[1] G. Yadigaroglu, “Two-Phase Flow Instabilities and Propagation Phenomena”. In: J. M.

Delhaye, M. Giot, M. L. Riethmuller, (Ed.), Thermohydraulics of two-phase systems for industrial design and nuclear engineering, Hemisphere Publishing Corporation,

Washington, 1981, pp. 353-396.

[2] S. Kakac, B. Bon, “A Review of two-phase flow dynamic instabilities in tube boiling systems”, International Journal of Heat and Mass Transfer, 51, 2008, pp. 399-433.

[3] G. Yadigaroglu, A. E. Bergles, “Fundamental and Higher-Mode Density Wave

Oscillations in Two-Phase Flow”, Journal of Heat Transfer, Trans. ASME, 94¸1972, pp.

189-195.

[4] Rizwan-uddin, “Physics of Density Wave Oscillations”, International Conference on New Trends in Nuclear System Thermohydraulics, Pisa, Italy, May 30-June 2, 1994.

[5] M. Z. Podowski, “Instabilities in Boiling Systems”, Third International Topical Meeting on Nuclear Plant Thermal Hydraulics and Operations, Seoul, Korea, November, 1988, pp.

A1-88-A1-98.

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[6] W. Ambrosini, P. Di Marco, J. C. Ferreri, “Linear and Nonlinear Analysis of Density Wave Instability Phenomena”, International Journal of Heat and Technology, 18, 1, 2000, pp. 27-36.

[7] W. Ambrosini, J. C. Ferreri. “Analysis of Basic Phenomena in Boiling Channel

Instabilities with Different Flow Models and Numerical Schemes”, Proc. 14th International Conference on Nuclear Engineering (ICONE 14), Miami, Florida, USA, July 17-20, 2006.

[8] D. B. Collins, M. Gacesa, “Hydrodynamic Instability in a Full Scale Simulated Reactor Channel”, Proc. of the Symposium on Two Phase Flow Systems, Leeds, Institute of Mechanical Engineers, London, 1969, pp. 117-128.

[9] U.S. NRC Nuclear Safety Analysis Division, “RELAP5/MOD3.3 Code Manual”, NUREG/CR-5535/Rev 1, December, 2001.

[10] M. Ishii, N. Zuber, “Thermally Induced Flow Instabilities in Two Phase Mixture”, Proc.

4th International Heat Transfer Conference, Paris, France, 1970, vol.5, paper B5.11.

Reference

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