Choking Flow

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    Historically, probably the most commonly-studied cases of two-

    phase flow are in large-scale power systems. Coal and gas-fired

    power stations used very large boilers to produce steam for use inturbines. In such cases, pressurised water is passed through

    heated pipes and it changes to steam as it moves through the

    pipe. The design of boilers requires a detailed understanding of

    two-phase flow heat-transfer and pressure drop behaviour, whichis significantly different from the single-phase case.

    Even more critically, nuclear reactors use water to remove heat

    from the reactor core using two-phase flow. A great deal of study

    has been performed on the nature of two-phase flow in such

    cases, so that engineers can design against possible failures in

    pipework, loss of pressure, and so on (a loss-of-coolant

    accident (LOCA))

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    Three types of Water reactors are there

    1>Pressurized Water reactor

    2>Boiling Water Rector

    3>LMFBR

    But Pressurized Water Rector is used in major nuclearpower plants. The coolant for nuclear power plant is

    water and that circulates through a heat exchanger by

    a pump.

    As the water reaches the boiling temperature (form

    two phase mixture) by heat of the nuclear rods(Fuel

    Rods) the deep pressurizer pressurize the water tobecame subcooled (compressed liquid) at high

    pressure.

    At high pressure at temperature corrosion can

    occur result into pipe break or crack or leakage.

    Loss of coolant accident (LOCA) can takes placewhich result into very dangerous effect. We are

    aware of fukushima accident in Japan. The reason

    behind that accident was Loss of coolant.

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    The rate of coolant blow down through a break

    or a leak is most important to design the

    Emergency Core Cooling System (ECCS).

    Rate of coolant blow down determine

    depressurization rate and the time of reactorfuel uncovery.

    The mass flux discharge depends upon the leak or break configuration , Upstream condition,

    thermodynamic property and it tend to be choke and hence maximum flow rate.

    1> Homogeneous equilibrium (same velocity and same property)

    2>Homogeneous non-equilibrium (same velocity and different property)

    3>non-Homogeneous equilibrium (different velocity and same property)3>non-Homogeneous non-equilibrium (different velocity and different property)

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    We shall first discuss the physical characteristic of critical flow under subcool inlet flow

    conditions. Next based upon the observed characteristics, flashing process will be

    defined and critical flow conditions will be predicted.

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    General Model:Assuming two phase flow through a pipe with equal phase velocity (Homogeneous) and

    thermodynamic equilibrium exist between vapor and liquid (Equilibrium).

    To formulate the two phase flow phenomenon, the bernaulis equation, in its generalform of the enery balance for the flow of unit mass of fluid, can written as

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    Now, this is basic design for pipe break.

    Based on this design we simplify the mass

    Flux equation.

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    Critical Two Phase Flow : Critical Overview

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    Critical Two Phase Flow : Critical Overview

    In HEM, we assume the vapor and liquid are in thermodynamic equilibrium and having

    same velocity. HEM gives good calculated value of mass flux for long pipes, so that

    thermodynamic equilibrium can achieve. But break or leak can happen at hi-

    pressure/temperature side mean near to the core. Hence HEM could not be the best

    model but sufficient to fulfill the purpose of ICCS (Emergency core cooling system designed

    on HEM calculations.As we done our previous calculation, we here assuming that our upstream conditions are

    subcooled and all the processes are isentropic. We will use predictions of Levy, Starkman,

    R.E. Henry and other paperwork.

    Our assumptions are based upon Moody and

    Henry-Fauske model.

    Gmax is critical flow rate obtained at nozzle/orifice exit. C is sonic velocity and b is

    dimensionless parameter. is P/Po. y is specific heat ration of vapour phase. K is slip ratio

    u(l) / u(g).

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    Comparison between experimental data and

    HEM and HNEM with changing stagnationsteam quality at particular instant of time.

    Time varying analysis of mass flow rate

    With orifice diameter 300mm and L/Dratio L/D=1

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    Comparison between observed mass flux with calculated

    mass flux of HEM and HNEM

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