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    Nuclear Engineering and Design 215 (2002) 187198

    Theoretical and experimental study on density waveoscillation of two-phase natural circulation of low

    equilibrium quality

    Su Guanghui a,b,*, Jia Dounan a, Kenji Fukuda b,1, Guo Yujun a

    a Xian Jiaotong Uni6ersity, 710049, Peoples Republic of Chinab Kyushu Uni6ersity, Hakozaki 6-10-1, Higashi-ku, Fukuoka, Japan

    Received 14 March 2001; received in revised form 20 March 2001; accepted 19 October 2001

    Abstract

    A theoretical and experimental study of density wave oscillation (DWO) in natural circulation is presented in this

    paper. Experiments were performed on a natural circulation test facility. The influences of mass flow rate, pressure,

    inlet subcooling, heat flux and exit quality on DWO were analyzed. The marginal stability boundary (MSB) of DWO

    was obtained. A criterion of two-phase natural circulation, which predicts the stability thresholds, was developed by

    lumped parameter method. It is a function of non-dimensional parameters, such as phase change number Npch,

    subcooling number Nsub, Froude number, Fr, geometry number Nl and friction number ~. The geometry number and

    friction number are first defined in this paper. A correlation of DWO period was also obtained, it is also a functionof the above non-dimensional parameters. The results of the present criterion and period correlation were compared

    with those of the experimental data and references. It is shown that they agree very well. 2002 Elsevier Science B.V.

    All rights reserved.

    www.elsevier.com/locate/nucengdes

    1. Introduction

    The flow instabilities and thermo-hydraulic os-

    cillations have long been studied and many works

    have been performed by many researchers since

    flow excursion was first discovered by Ledinegg in1938, Ledinegg (1938). These studies were

    prompted by potential harmfulness caused by

    instabilities in large-scale nuclear reactor systems.

    The 1979 accident at Three Mile Island (TMI)

    reactor proved the importance of the concept of

    inherent reactor safety. Passive residual heat re-

    moval systems (PRHRS) have been adopted such

    as in JPSR (Murao et al., 1995) and AP600(Mcintyre and Beck, 1992) reactors. Natural cir-

    culation is used in some PRHRSs such as in

    AC600 (Su et al., 1994) provided by China. The

    natural circulation can also be used in the primary

    side of such reactors as the low temperature heat-

    ing reactor (THR; Wang, 1993). Boiling natural

    circulation is the major cooling mechanism in the

    * Corresponding author. Tel.: +86-29-266-7082; fax: +86-

    29-266-7802.

    E-mail addresses: [email protected] (S. Guanghui), sugh@

    nucl.kyushu-u.ac.jp (K. Fukuda).1 Tel./fax: +81-92-6423789.

    0029-5493/02/$ - see front matter 2002 Elsevier Science B.V. All rights reserved.

    PII: S 0 0 2 9 - 5 4 9 3 ( 0 1 ) 0 0 4 5 6 - 3

    mailto:[email protected]
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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198188

    SBWR (Barbucci, 1995). Flow in natural circula-

    tion systems is induced by difference in fluid

    densities between the hot leg (riser) and the cold

    leg (downcomer). For a two-phase natural circula-

    tion loop, heat input and its removal induces a

    large volumetric change owing to phase changes-

    boiling and condensation-, thus the system easily

    becomes unstable. In such a two-phase naturalcirculation loop, various types of flow instabilities

    occur depending on the system geometry, fluid

    properties and the operating conditions etc. One

    of the most important phenomena in natural cir-

    culation loop is density wave oscillation (DWO)

    which can affect the operation and safety features

    of the system. That is, the self-sustained DWO

    may cause many undesired problems such as me-

    chanical and thermal fatigue of components by

    mechanical vibration and thermal waves to re-

    quire the system control considerations.There are many studies dealing with two-phase

    oscillations. A large part of the studies is on

    forced circulations and relatively less works

    (Wissler et al., 1956; Chexal and Bergles, 1973;

    Ardron, 1984; Lee and Ishii, 1998; Balunov, 1990;

    Delmastro et al., 1991; Yun, 1994 etc.) have been

    done on natural circulation. Boure et al. (1973)

    made a clear classification of flow instabilities.

    But most of the instabilities mentioned by Boure

    concerned forced circulation. Fukuda and Kobori

    (1979) classified DWO into two types, namely,

    type I and II. Type I is the DWO occurring at low

    quality conditions, for which gravitational pres-

    sure drop in unheated riser plays a dominant role;

    and Type II is one occurring at high quality

    conditions, for which frictional pressure drop is

    dominant. Lee (1991), studied the flow instabili-

    ties in an open two-phase natural circulation loop

    and constructed typical instability map. Kyung

    and Lee (1994) investigated flow characteristics in

    an open two-phase natural circulation loop with

    Freon-113 as the working fluid and observed

    three basic circulation modes (periodic circulation

    A, continuous circulation and periodic circulation

    B) with variation of the heat flux and constant

    inlet subcooling. Further, Kim and Lee (2000)

    classified natural circulations into six different

    modes. Instability map in the plane of the heat

    flux and the heater-inlet subcooling was plotted.

    Rohatgi and Duffey (1998) presented critical sub-

    cooling number as a function of Froude number,

    Fr in natural circulation two-phase flow and

    showed the fundamental parametric dependencies

    on the loop loss coefficient and the ratio of the

    heated channel to downcomer heights. Inada et al.

    (1995, 1997, 2000) studied two-phase flow insta-

    bility in a boiling natural circulation loop atrelatively high system pressure and analyzed the

    inlet throttling effect on flow stability. Zhou

    (1997), Jiang et al. (2000) studied stability struc-

    ture of low quality DWO in a natural circulation

    system at heating reactor conditions by the fre-

    quency domain method. Su (1997), Su et al.

    (2001) presented a non-linear dynamic model in

    time domain of two-phase natural circulation.

    But unfortunately, there is not a perfect crite-

    rion to predict the stability of two-phase natural

    circulation, neither a period correlation to calcu-late DWO period. The main purpose of this paper

    is to derive the stability criterion and period cor-

    relation of two-phase natural circulation. Experi-

    mental study was also done to verify the criterion

    and correlation.

    2. Experimental investigation

    2.1. Test facility

    The schematic diagram of the test system is

    shown in Fig. 1. Basically it consists of the pri-

    mary loop, secondary loop (cooling loop), electri-

    cally heating system and measuring system. The

    primary loop is a two-phase natural circulation

    one, which consists of pre-heater, test section,

    riser, condenser, downcomer, pressurizer, throttle

    valve, and connection tubes. All of the compo-

    nents and tubes were made of stainless steel.

    Table 1 shows the main parameters of the natural

    circulation loop and test section.

    Distilled water was used as working fluid. It

    enters the heated test section with the required

    conditions; exits as two-phase mixture and flows

    through the riser into the condenser, through the

    downcomer, the throttle valve and pre-heater

    where it reaches the specified subcooling, then it

    flows back into the inlet of the test section.

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198 189

    Fig. 1. The natural circulation loop.

    Table 2

    Ranges of main parameters of experiment

    Parameter UnitRange

    Pressure 0.22 MPa

    Inlet subcooling C540

    Mass flow rate kg s100.4

    03540 kg m2

    s1

    Mass velocity230 kWHeat power of test section

    ference (drop) of the test section was detected by

    a pressure transducer. The fluid temperatures of

    the test section inlet and outlet, and the outside

    wall temperatures were detected by thermocou-

    ples. The heated power was calculated from the

    coefficient of heat balance, the voltage and the

    current of power supply. All of the experimental

    data were recorded by a data acquisition system.

    The mass flow rate, pressure difference between

    the test section inlet and outlet, the fluid tempera-

    ture of the test section inlet, the pressures of the

    test section inlet and outlet and the wall tempera-

    ture were recorded by a multi-channel data

    recorder. The ranges of the main experiment

    parameters are listed in Table 2.

    2.2. Results

    Under the specified run conditions, the DWO

    will occur if the heated power increases step by

    step. The state of the system is very sensitive to

    the fluctuations of heated power when the system

    run conditions are near to the unstable region.

    Although the power increment is very small, it

    can cause the self-sustained oscillations in the

    system mass flow rate, test section pressure differ-

    ence, wall temperatures and fluid temperature etc.

    The oscillation periods are short (240 s), there-

    fore, the frequencies are high. The shapes of these

    oscillations are quite regular, the amplitudes are

    identical. The wall temperature and the mass flow

    rate oscillate out of phase, i.e. with a 180 phase

    lag, the pressure difference and the mass flow rate

    oscillate in phase. For the same conditions, if the

    power is relatively small, the periods of oscillation

    are long, and in the same time, there are smaller

    fluctuations in which the period is shorter than 1

    The mass flow rate G, system pressure P, the

    temperatures of test section inlet Tin and outlet

    Tex, the temperatures of test section outside wall

    Tw, heated power Q, and the pressure difference

    between test section inlet and outlet were mea-

    sured and recorded during experiments. The natu-

    ral circulation mass flow rate was measured by a

    orifice flow meter and the differential pressure

    transmitter. The pressure of the system was mea-

    sured by a pressure transducer. The pressure dif-

    Table 1

    Main parameters of natural circulation loop

    UnitParameters Value

    mTotal height of loop 12

    9.5 mHeight between the center of hot and

    cold sources

    Size of riser tube 342.5 mm

    Height of riser 7.5 m

    11Height of downcomer m

    Size of test section tube 162 mmLength of test section m3

    mmLength of heated section 670

    Power of condenser 350 kW

    Power of test section 180 kW

    150Power of pre-heater kW

    Mass flow rate 5 kg s1

    16Pressure of system MPa

    250Temperature of fluid C

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198190

    s. When the power increases, the period of fluctu-

    ation decreases, the oscillations increase, e.g. the

    amplitude and the mean magnitude of mass flow

    rate also increase.

    2.2.1. Effect of system pressure

    System pressure can influence the system insta-

    bility, as shown in Fig. 2. Keeping other parame-

    ters such as mass flow rate, inlet subcooling etc.

    constant, the critical power (heat flux) will in-

    crease if system pressure increases. Critical power

    is defined as the heated power when the system

    begins to oscillate. The system stability will be

    improved if the critical power increases. For the

    same conditions, and identical increase of heated

    power, the disturbance of gravitational pressure

    drop under the conditions of high pressure is less

    than that of low pressure because the density

    difference between the liquid phase and vapor

    phase will decrease if the system pressure in-

    creases. In this case, the self-sustained oscillation

    of mass flow rate can not be continued, or it can

    not be produced, so the system tends to be stable.

    The system pressure has no obvious influence on

    the DWO period, but the DWO amplitude will

    decrease and the DWO period will increase a little

    if the system pressure increases, as shown in Fig.

    3. Also, the critical exit equilibrium quality, which

    is defined as the exit equilibrium quality when

    oscillation occurs, will increase with an increase of

    pressure, as shown in Fig. 4.

    2.2.2. Effect of inlet subcooling

    The inlet subcooling has a complex, nonlinear

    influence on DWO, as shown in Fig. 5. On the

    Fig. 3. The influence of system pressure on the period of

    oscillations.

    one hand, if the inlet subcooling increases, the

    length of single phase of liquid (or single phase

    region) in the test section will increase. If theincreasing of inlet subcooling equals to the in-

    creasing of the inlet resistance coefficient, the

    stability of the system will increase. On the other

    hand, for constant heat flux, if the inlet subcool-

    ing increases, the average quality of the test sec-

    tion will decrease, the period of bubble producing

    will increase, evaporated time will increase, the

    responding time that inlet mass flow rate responds

    to change of pressure difference due to the evapo-

    ration will decrease, and a DWO may occur.Thus, if the first mechanism is predominant, the

    system tends to be stable if the inlet subcooling

    Fig. 4. The influence of system pressure on critical exit equi-

    librium quality.Fig. 2. The influence of system pressure on stability.

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198 191

    Fig. 5. The influence of inlet subcooling on stability.

    Fig. 7. The influence of mass flow rate on critical exit equi-

    librium quality.

    mass flow rate has strong cooling action to the

    wall of the test section, it is difficult for bubbles

    agglutination. But the increasing of mass flow rate

    will result in the decreasing of the exit equilibriumquality, as shown in Fig. 7. So the DWO will

    occur at the low exit equilibrium quality under

    high mass flow rate. Under these conditions, the

    average density of fluid increases, the circulation

    time of the fluid through the test section will

    become longer, so the DWO period will increase,

    as shown in Fig. 8. With the same enthalpy

    increment per unit fluid, the increase of mass flow

    rate will result in the increase of oscillation ampli-

    tude of parameters such as mass flow rate, pres-

    sure difference of the test section, and tempera-ture. Fig. 9 shows the oscillation amplitude

    changes with mass flow rate.

    increases. If the second one is predominant, the

    system tends to be unstable if the inlet subcooling

    increases. Indeed, there is a critical inlet subcool-ing. When the inlet subcooling is smaller than this

    critical inlet subcooling, the system stability will

    decrease when the inlet subcooling increases. And

    on the other hand, when the inlet subcooling is

    bigger than the critical inlet subcooling, the sys-

    tem stability will be increased if the inlet subcool-

    ing increases. The critical inlet subcooling is about

    20 C in the experiments.

    2.2.3. Effect of mass flow rate

    If mass flow rate increases, the critical powerwill increase, so the system will tend to become

    stable, as shown in Fig. 6, since the fluid at high

    Fig. 6. The influence of mass flow rate on stability.

    Fig. 8. The influence of mass flow rate on the period of

    oscillations.

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198192

    Fig. 9. The influence of mass flow rate on oscillation ampli-

    tude. Fig. 11. The influence of exit equilibrium quality on the period

    of oscillations.

    2.2.4. Effect of heat flux and exit quality

    Keeping the main parameters such as system

    pressure, mass flow rate and inlet subcooling etc.

    constant, the factor which decides whether the

    system is stable or not will be the heat flux. Thesystem tends to be unstable with an increasing

    heat flux. In the steady-state, the increase of heat

    flux will make the natural circulation mass flow

    rate increase. The averaged value of mass flow

    rate will also increase with increasing heat flux

    when DWO occurs. Moreover, the oscillation am-

    plitude will also increase. The amplitude of wall

    temperature is not big but its frequency is the

    same as that of mass flow rate fluctuation. So the

    characteristics of wall temperature oscillation are

    low amplitude and high frequency. The oscillation

    period will become short with an increase of heat

    flux, as shown in Fig. 10. It also will become short

    with an increase of exit equilibrium quality, as

    shown in Fig. 11. With the increasing heat flux,

    the exit equilibrium quality will increase, the aver-

    aged fluid density will decrease, the mass velocity

    in the test section will increase, the time when the

    fluid stays in the test section will become short, sothe period of oscillation will also be reduced. But

    in high heat flux region, the change of period will

    be small and almost tends to be flat with an

    increase of heat flux.

    2.2.5. Marginal stability boundary

    The above analyses were done under the condi-

    tions of keeping all of the parameters constant

    except the one whose effect on the stability will be

    studied. If all of the parameters charge it will be

    difficulty to analyze the influence effects of

    parameters on stability because there are many

    parameters which can affect the stability. So non-

    dimensional parameters, which include all of the

    parameters that can affect the stability, are helpful

    to analyze the influence effects of parameters. In

    this paper, phase charge number Npch, subcooling

    number Nsub, and Fr are employed, and their

    definition are given by Eqs. (18), (17) and (19))

    respectively. The marginal stability boundary

    (MSB) can be shown by the above non-dimen-

    sional parameters. The MSB shown by Npch ver-

    sus Nsub plane is plotted in Fig. 12. In general,

    Nsub will increase with an increase of Npch. When

    Npch\Nsub, net vapor will be produced in the

    system, and the quality will increase with the

    increasing (NpchNsub). The MSB in Fig. 12 is

    for type I DWO because the experiments were

    done under low equilibrium quality. In Fig. 12,Fig. 10. The influence of heat flux on the period of oscillations.

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198 193

    the results of references are also shown. The

    difference between this paper and references may

    be due to the differences of test loops. The MSB

    as a function of Npch, Nsub and Fr is plotted in

    Fig. 16.

    3. Stability criterion

    The most different aspect of the natural circula-

    tion mode from the forced circulation one is that

    the mass flow rate is determined by the heated

    power. The bigger the mass flow rate is, the

    stronger the natural circulation ability is. Thus, a

    riser, which is also called a chimney, is always

    employed in a natural circulation as shown in Fig.

    1 to increase the mass flow rate. So consider the

    boiling channel of the natural circulation loop,

    which is divided into three control volumes asshown in Fig. 13. The above control volume is the

    riser (chimney), the bottom one is single phase

    flow region and the middle one is two-phase flow

    region. The interface between the single phase

    flow and two-phase flow region will be changeable

    with the change of run conditions, so the length

    of these two control volumes will also be change-

    able. To simplify the analysis, the governing equa-

    tions, which describe the interaction between the

    liquid and vapor phase, are based the following

    hypothesis (Guido et al., 1991; Su, 1997):Fig. 13. Boiling channel of natural circulation.

    1. the subcooling region is neglected because its

    length is very short;

    2. the heat flux of the channel is constant;

    3. the friction pressure drop for single phase flow

    is concentrated on the inlet of this channel and

    the friction pressure drop for two-phase flow is

    concentrated on the outlet of this channel;

    4. the homogeneous phase flow is used as two-

    phase flow model;

    5. the temperature distribution in single phase

    flow region is linear.

    The basic conservation equations of mass and

    energy can be written as following.

    For single phase (liquid) flow mass conserva-

    tion equation:

    AzsdZsp

    dt=WinWsp (1)

    Fig. 12. MSB of DWO.

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198194

    Energy conservation equation:

    Azsd

    dt(Zsphsp)=WinhinWsphs+Q

    Zsp

    Z(2)

    For two-phase flow mass conservation

    equation:

    A ddt

    (ztpZtp)=WspWout (3)

    Energy conservation equation:

    Ad

    dt(ztphtpZtp)=WsphsWouthtp+Q

    Ztp

    Z(4)

    The action of gravitation is very important in

    natural circulation, so momentum conservation

    equation can be written as:

    (Kin2)sWin2 +(Kout+2) tp

    2 Wout2 +2zgZA2

    =2A2DP (5)

    in which the equation of state, that is, the rela-

    tionship between enthalpy and density will be as

    follow when system pressure is constant(Guido et

    al., 1991; Su, 1997).

    z=s+hhs

    hfg

    fgn1

    h\hs (6)

    z=zs h5hs (7)

    Furthermore, the following parameters are

    defined to obtain the non-dimensional parame-

    ters:

    Zd=Z (8)

    td=zsZA

    Wo(9)

    Wd=Wo (10)

    Hd=Q

    Wo(11)

    Eq. (1) can be written in non-dimensional form:

    AzsdZsp

    dt=Azs

    dZsp

    d(t/td)

    1

    td=Wo

    dZ(tp

    dt(=WinWsp

    (12)

    dZ(sp

    dt(=W( inW( sp (13)

    Similarly, Eqs. (2)(4) are rewritten as follows:

    d

    dt((Z(sph(sp)=W( inh(inW( sph(s+Q(Z(sp (14)

    d

    dt((ztpZ(tp)=W( spW(out (15)

    d

    dt((ztpZ(tph(tp)=W( sph(sW(outh(tp+Q(Z(tp (16)

    Furthermore, the following non-dimensional

    parameters are defined:

    Subcooling number:

    Nsub=Dhinfg

    hfgf(17)

    Phase change number:

    Npch=Qfg

    Wfhfg(18)

    Friction number:

    ~=2(Kin+Kout)

    Kout+2(19)

    Froude number, Fr:

    Fr=V2

    gL(20)

    Geometry number:

    Nl=Zr

    Z(21)

    The above equations are perturbed around

    steady state and applying these non-dimensional

    parameters, one finds:

    d

    dtlZsp=

    4

    ~

    Npch2

    Npch

    2(1+NpchNsub)Fr(Kout+2)

    nlhtp

    +4Npch

    ~ 2

    Npch

    NsublZsp (22)

    d

    dtlhtp=

    Npch(1+NpchNsub)

    (1Nl)NpchNsub

    1~

    (NpchNsub)

    11

    (1+NpchNsub)Fr(Kout+2)

    1

    nlhtp

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198 195

    +Npch(1+NpchNsub)

    (1Nl)NpchNsub

    12

    (NpchNsub)4~

    1

    Nsub

    Npch

    Nsub

    nlZsp

    +((2/~)(NpchNsub)1)NlNpch(1+NpchNsub)

    (1Nl)NpchNsub

    (23)

    A system of nonlinear partial differential equa-

    tions is constituted by Eqs. (22) and (23), and its

    general solution is as:

    X=Xoexp(ut)+X1 (24)

    Where X=

    lZsp

    lhtp

    is a determinant; Xo is a

    constant matrix, and X1=

    f1(t)

    f2(t)

    is its charac-

    teristic solution.

    Introducing the following parameters in order

    to convenience for writing:

    A1=4

    ~

    Npch2

    Npch

    2(1+NpchNsub)Fr(Kout+2)

    (25)

    A2=4Npch

    ~

    2Npch

    Nsub(26)

    A3=Npch(1+NpchNsub)

    (1Nl)NpchNsub 1~ (NpchNsub)

    11

    (1+NpchNsub)Fr(Kout+2)

    1

    n(27)

    A4=Npch(1+NpchNsub)

    (1Nl)NpchNsub

    12

    (NpchNsub)

    4~

    1

    Nsub

    Npch

    Nsub

    n(28)

    The characteristic equation of homogeneousequation of inhomogeneous differential equations

    is:

    uA2 A1

    A4 uA3

    = (uA2)(uA3)A1A4

    =0 (29)

    That is:

    u2+Cu+D=0 (30)

    C= (A2+A3) (31)

    D=A2A3A1A4 (32)

    If:C\0 and DB0 (33)

    is satisfied, the system will be unstable under the

    conditions of low quality, that is, the MSB ob-

    tained by Eq. (33) will be located in the low

    quality region. So the oscillation will be type I in

    this case. That is, the DWO (Type I) will occur if

    C\0 and DB0.

    And if:

    CB0 and D\0 (34)

    is satisfied, the system will also be unstable, but it

    is under the conditions of high quality, that is to

    say, the MSB obtained by Eq. (34) will be located

    in the region of high quality. So the oscillation

    will be type II in this case. That is to say, DWO

    (Type II) will occur if CB0 and D\0.

    The nondimensional frequency is:

    f(=D (35)Thus, the period of DWO is (Guido et al., 1991;

    Su, 1997):

    T=2y

    f(td (36)

    We can obtain the MSB of DWO using this

    criterion expressed by Eqs. (33) and (34). The

    results of Eq. (33) were compared with those of

    experiments and RETRAN02 (Gao and Li, 1989),

    see Figs. 1417. Figs. 14 and 15 are plotted in

    Npch versus Nsub, Fig. 16 is plotted in the NpchFr0.5 versus Nsub, in which both the MSBs of type

    I DWO obtained from experiments and criterion

    and the MSBs of type II DWO obtained from

    criterion were shown. Fig. 17 are also plotted in

    the Npch Fr0.5 versus Nsub which shows a compari-

    son between MSBs obtained by criterion and

    RETRAN02. The figures show that the MSBs

    obtained by criterion agreed well with the results

    of experiments and reference (Gao and Li, 1989).

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198196

    Fig. 14. Comparison between MSBs obtained by criterion and

    experiments (A).

    Fig. 16. Comparison between MSBs obtained by criterion and

    experiments (C).

    The period obtained analytically by Eq. (36)

    was compared with the results of experiments,

    and it was in good agreement with the results of

    experiments, as shown in Fig. 18.

    4. Conclusions

    DWO is quite an important phenomenon in

    natural circulation and it can be classified into

    two types. The type I DWO is experimentally

    studied in this paper. Experiments were per-

    formed on a natural circulation test facility.

    The system will tend to be stable if the systempressure increases. The system pressure has no

    obvious influence on DWO period, but the

    DWO amplitude will decrease and the DWO

    period will increase a little if the system pres-

    sure increases. The critical exit equilibrium

    quality will increase with an increase of

    pressure.

    The inlet subcooling of the test section hasobvious, complex, nonlinear influence on

    DWO. There is a critical inlet subcooling which

    is about 20 C. When the inlet subcooling is

    smaller than this critical inlet subcooling, the

    system stability will decrease when the inlet

    subcooling increases. And when the inlet sub-

    cooling is bigger than the critical inlet subcool-

    ing, the system stability will be increased if the

    inlet subcooling increases.

    If mass flow rate increases, the system will tend

    to be stable. The critical exit equilibrium qual-ity will decrease, the DWO period will increase

    and DWO amplitude will increase with the

    increase of mass flow rate.

    With the increasing of heat flux, system tendsto be unstable and the period of DWO be-

    Fig. 15. Comparison between MSBs obtained by criterion and

    experiments (B).

    Fig. 17. Comparison between MSBs obtained by criterion and

    RETRAN02.

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198 197

    Fig. 18. Comparison between results obtained by correlation and experiments.

    comes short. But in the conditions of high heat

    flux, the change of period will be small and

    almost tends to be flat.

    The maps of MSB for type I DWO in theplane of Nsub and Npch, and of Npch Fr

    0.5 and

    Nsub were obtained.

    The theoretical study was also presented in this

    paper.

    The boiling channel of natural circulation isdivided into three control volumes. The non-

    dimensional changes are done to the basic

    mass, energy and momentum conservation

    equations.

    A criterion for predicting stability and a corre-lation of DWO period are obtained. The re-

    sults obtained by the criterion and the

    correlation agreed well with those of experi-

    ments and reference.

    The MSB maps for both type I DWO and typeII DWO can be obtained by the criterion.

    5. Nomenclature

    A cross sectional area

    gravitational accelerationg

    mass flow velocityG

    specific enthalpyh

    friction coefficientK

    heat lengthL

    pressureP

    heat fluxq

    Q heated power

    timet

    velocityV

    W mass flow rate

    axial coordinatez

    void fractionh

    z density

    specific volume

    Subscripts

    f liquid

    transfer from liquid to vaporfg

    g vaporinletin

    outletout

    steady-stateo

    riserr

    s saturated

    single-phase flowsp

    two-phase flowtp

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    S. Guanghui et al. /Nuclear Engineering and Design 215 (2002) 187198198

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