Modelling and Simulation of LOCA

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    With great pleasure and deep sense of gratitude, we express our indebtedness to our

    respected Sir Mr. Sandip Ghosh for his invaluable guidance and constant

    encouragement at each and every step of our project work. He gave all the

    requirements that we had to implement in the project in very structured manner, not

    only that he helped us through proper analysis and discussions but always showed

    great interest in providing timely support and suitable suggestions.

    Last but not least we would like to thank Mr. Malay Kr Banerjee HOD, Mechanical

    Dept for his encouragement, support and help us in completing this program

    successfully.

    Thanking you,

    Subhra Roy

    Shangarab Bera

    Partha Sarathi Ghosh

    Souvik Das

    Nilkanta Mahato

    Amit Roy 3

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    1. AIM OF THE PROJECT.

    2. PROJECT PLAN.

    3. BASICS OF LOCA.

    4. FLASHING FLOW.

    5. BASICS OF FINITE

    ELEMENT ANALYSIS.

    6. WHAT IS ANSYS?7. WORKS ACHIEVED.

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    1) A compressible two phase domain modeling for a typical pipe crack will be approachedby using ANSYS design modeler and FLUENT two phase flow setups using cavitation

    subroutines.

    2) The Void fraction or the volume fraction of the flashing phase at outlet as well as the flow

    Mac No. for several upstream stagnation conditions are to be calculated and compared with

    standard experimental results or analytical predictions on flashing flow or those specific toLOCA accidents.

    3) Pressure distribution through the narrow slit channel ( looks like a short duct of minute

    width) are to be found to know the flashing inception point for judging the flashing flow

    domain properly.

    4) Critical leakage flow rates through modeled slit will be an important findings related to

    leak detection and plant safety shutdown factors. Effect of friction in channels can also be

    separately investigated.

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    A loss-of-coolant accident (LOCA) is a

    mode of failure for a nuclear reactor;

    if not managed effectively, the results

    of a LOCA could result in reactor core

    damage.

    Nuclear reactors generate heat

    internally; to remove this heat and

    convert it into useful electrical power,

    a coolant system is used. If this coolantflow is reduced, or lost altogether, the

    nuclear reactor's emergency shutdown

    system is designed to stop the fission

    chain reaction.

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    A PWR primary system is shownin Figure. The design basis

    accident in the PWR is a double-

    ended guillotine break in a cold

    leg between the reactor coolant

    pump and the reactor vessel.

    The average peak cladding

    temperature (PCT) during the

    blow down phase of a large-

    break LOCA is approximately 1

    500F (815C) and the PCT at95% confidence level is about 1

    750F (954C), assuming a loss-

    of-offsite power and the worst

    single failure assumption for the

    emergency core cooling system.8

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    The refill period occurs

    between 30 and 40 s following

    the start of the LOCA.

    The reflood period occursbetween 40 and 200 s

    Zirconium-water reactions

    can occur for high

    temperature regions of the

    core

    The average reflood PCTduring this period is

    approximately 1 680F

    (915C) and the PCT at 95%

    confidence is about 1 975F

    (1 080C)

    The maximum amount of

    cladding oxidized at a given

    location during this phase of

    the LOCA is about 10% for

    beginning-of-life (BOL) UO2

    fuel and the total oxidation is

    less than 1%.

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    Various LOCA tests were conductedat LSTF, the world's largest plant

    simulator with the same height and

    1/48 volume of a 3423 MWt PWR, to

    examine the effectiveness of accident

    management (AM) measures if there is

    severe loss of coolant. In case of HPI total failure, it is

    important for operators to depressurize

    the primary coolant system by opening

    SG relief valves (RVs) to activate the AIS

    and LPI system.

    The tests verified the effectiveness ofthis AM measure even in a LOCA caused

    by vessel bottom break which is the

    worst break location.

    A code analysis also confirmed the

    effectiveness.

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    The design basis accident for a

    BWR-6 is a double-ended breakin the suction-side of the

    recirculation line. Shortly after the

    break, the reactor scrams,

    typically on drive flow pressure.

    Because of the large flow

    reductions immediately followingthe LOCA caused by the

    depressurization, there is a rapid

    increase in the core average void

    fraction. The negative void

    reactivity rapidly shuts down the

    core. The flow reverses in thebroken loop jet pump. With the

    flow reversal all the drive flow to

    that jet pump is lost and one-half

    the drive flow that is supporting

    the core flow is lost.13

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    Valves are closed to isolate

    the system, typically within

    four seconds after the LOCA.

    As the LOCA and

    depressurization continue , the

    level inside the core region

    decreases, as well as forming a

    level in the lower plenum region.

    Within 35-40 s following the

    LOCA, the high pressure core

    spray system begins to delivercoolant to the top of the core, the

    time being determined by the

    time to start the diesel generator

    that drives the high pressure core

    spray system.

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    In a CANDU reactor, the fuel is loaded

    into horizontal pressure tubes, and is cooled

    by the flow of pressurized heavy water,

    In broad terms, a LOCA in a CANDU

    follows a similar sequence to that described

    for a PWR. A break in the heat transport

    system initiates reactor shut down.

    Despite these similarities with the PWR

    LOCA sequence, the horizontal pressure tube

    design and heavy water moderator mean that

    the details of the accident progression are

    quite different.

    In the CANDU-6 design, the coolant void

    reactivity is positive but the coolant void

    reactivity is negative in the advanced CANDU

    reactor (ACR) design.15

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    The term flashing flow is reserved

    for the flow with dramatic

    evaporation of liquid due to a drop

    of pressure P. The process of

    production of the vapour phase is

    usually accompanied by massivethermodynamic and mechanical

    non-equilibrium by virtue of a

    difference in temperature and

    velocity of both phases.

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    This linear relationship

    does not always hold true.

    As the pressure drop is

    increased, the flow reaches a

    point where it no longer

    increases. Once thishappens, additional

    increases in pressure drop

    across the valve do not

    result in additional flow, and

    flow is said to be choked.

    Here we will call thislimiting or choking pressure

    drop the Terminal Pressure

    Drop, pT.

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    Conservation of energy dictates that

    since kinetic energy at the venacontracta has increased to a maximum,

    potential energy, in the form of static

    pressure, must decrease to a minimum.

    If the vena contracta pressure

    drops below the vapor pressure,vapor bubbles form at the vena

    contracta. Because vapor takes up a

    much larger volume that the liquid,

    the vapor bubbles fill the vena

    contracta and any additional lowering

    of the downstream pressure simply

    results in the bubbles getting bigger,

    but the flow does not increase. It is

    the formation of these bubbles in the

    vena contracta that causes the flow to

    become choked.19

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    As the bubbles move down stream, the

    cross sectional flow area opens up, the

    velocity goes down and the pressure goes

    up. Now we have bubbles with an internal

    pressure equal to the vapor pressure

    surrounded by a higher pressure. Thebubbles collapse in on themselves.

    This damage can happen very quickly,

    sometimes in as little as a few weeks or

    months. Because cavitation damage

    happens so quickly, we try to avoidcavitation at all costs. Very hard materials

    give some improvement, but usually the

    improved performance is not enough to

    justify the cost.

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    If we continue to decrease the downstreampressure, we reach a point where the pressure

    downstream of the valve is less than the vapor

    pressure of the liquid.

    The damage mechanism is a sand blastingeffect. Downstream of the vena contracta the

    flow consists of a large volume of vapor with

    many tiny drops of liquid. Because the volume

    increases greatly when liquid vaporizes,

    The noise caused by flashing is usually

    below 85 dBA and to the author's knowledge

    there is no method for calculating flashing

    noise.

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    In reality, at pressure drops

    approaching, but below the calculated

    value of pT, there is usually some

    formation of vapor bubbles and some

    degree of cavitation. Figure 5 shows

    what really happens as flow

    transitions from non-choked to fully

    choked flow.

    It is interesting to note that current

    control valve sizing methods do notinclude a method of calculating where

    the transition from non-choked to fully

    choked flow begins and ends.

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    The value ofpT is a

    function of both the

    process condition andthe valve's internal

    geometry represented

    by the experimentally

    determined Liquid

    Pressure Recovery

    Factor, FL.

    Higher values of FL are

    associated with valves

    that have a lower

    potential for cavitation,and smaller values of FL

    are associated with

    valves that have a greater

    potential for cavitation.

    A more reliable method of preventing cavitation damage

    in control valves, according to one major control valve

    manufacturer, is to avoid valve applications where the

    calculated noise exceeds limits based on a broad range of

    application experience. 23

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    Computational Fluid

    DynamicsThe physical aspects of any fluid flow are governed by the

    following three fundamental principles:

    1. Mass is conserved;

    2. Energy is conserved.

    3. It obeys the 2nd law of Newton.

    Computational fluid dynamics is, in part, the art of replacing

    the governing partial differential equations of fluid flow

    with numbers, and advancing these numbers in space

    and/or time to obtain a final numerical description of the

    complete flow field of interest.

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    Contd.

    Now in the previous slide the given expression isnot all inclusive about ANSYS.

    there are some applications which involve

    integral equations rather than partial differentialequations.

    all such problems involve the manipulation of,and the solution for, numbers.

    The end product of CFD is indeed a collection ofnumbers, in contrast to a closed-form analyticalsolution.

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    ANSYS is based on FEA ( Finite Element

    Analysis ). Before proceeding to obtain

    various solutions in it we should try to

    understand its working process very briefly.

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    WORKING PLATFORM OF ANSYS

    The purpose of Finite Element Analysis (all varieties) is to mathematicallymodel a physical problem that cannot be solved satisfactorily by other means.Typical reasons for difficulties in finding solutions are:-1. that manual means of mathematical modelling cannot represent the

    problem sufficiently accurately.

    2. that physical (real) models are deficient.3. that full size prototypes are far too expensive.

    In all Finite Element Analysis, the mathematical modelling of the problem is done by dividing the probleminto small pieces whose performance can be modelled simply; Finite (size)Elements.The relationships between each neighbouring element are controlled so that,taken as a whole, the Mesh of Finite Elements approximates to the originalproblem.

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    Contd..

    For small deflection, elastic, static structural

    analysis, the system is modelled as:-

    [K] {x} = {F} where

    [K] is the stiffness matrix

    {x} is the displacements (of the nodes)

    {F} is the forces (at the nodes)

    Solving this set of simultaneous equations yields

    the basis of the desired solution.

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    Contd..

    Many FEA systems are now often capable ofmodelling time varying quantities with nonlinearproperties and large changes in geometry.However the core of FEA analysis, and the mostreliable, is still the static structural analysislimited to:-

    elastic, homogeneous, isotropic materials

    linear material properties

    small deflections: geometry changes can beignored

    all material well below yield: no plasticdeformation

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    What is ANSYS?

    ANSYS is a general purposefinite element modelingpackage for numericallysolving a wide variety ofmechanical problems, used

    widely in industry to simulate

    the response of a physicalsystem to structural loading,and thermal andelectromagnetic effects.

    ANSYS uses the finite-element method to solve the

    underlying governingequations and the associatedproblem-specific boundary

    conditions.

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    ANSYS MODULES

    ANSYS can work integrated with other usedengineering software on desktop by adding CADand FEA connection modules.

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    Advancement in 13.0 version

    ANSYS 13.0 includes a great number ofnew and advanced features that make iteasier, faster and cheaper for customers to

    bring new products to market, with a highdegree of confidence in the ultimate resultsthey will achieve. The product suite deliversnew benefits in three major areas:

    * Greater accuracy and fidelity: As

    engineering requirements and designcomplexity increase, simulation softwaremust produce more accurate results thatreflect changing operating conditions over

    time.* Higher productivity: ANSYS 13.0 includesdozens of features that minimize the timeand effort product development teams investin simulation.

    * More computational power: For someengineering simulations, ANSYS 13.0 can

    provide speedup ratios that are five to 10times greater than previous softwarereleases. Even complex multiphysicssimulations can be accomplished morequickly and efficiently.

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    OUR WORK

    Started ANSYSworkbench 13.0 andcreated a new fluidflow analysis system

    in fluid flow(FLUENT)toolbar.This creates anew ANSYS FLUENT

    based analysis systemin the projectschematic.

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    DESIGN MODELER

    Started ANSYS DesignModeler and set the unitin mm.

    Created the geometry ofthe pipe and the crackformation within it bygiving certain dimensionand selecting suitable

    planes.

    Generated the geometry.

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    MESHING

    Opened the ANSYSMeshing application.

    Created name

    selections for geometryboundaries.

    Set some basicparameters for the

    ANSYS meshingapplication.

    Generated the mesh.

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    FLUENT

    Proceeded to setting up aCFD analysis Using

    ANSYS FLUENT.

    Enabled the properoptions,

    Set some general settingsfor simulation and alsothe models,material

    settings, cell zoneconditions, boundaryconditions.

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    Continued.

    Set the solutions for the CFD simulation.

    Changed the convergence criteria for the continuity

    equation residual. Calculated a solution.

    Started a calculation by requesting 250 iterations.

    As the calculation processes ,the residuals plotted inthe graphics window.

    Solution is converged after 180 iterations.

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    Some instant shots..38

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    Some more.39

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    Results and termination

    Displayed results inANSYS FLUENT.

    Displayed filled contours

    of pressure in all planes. After displaying the result

    Closed the ANSYSFLUENT and checked the

    all generated file write ornot in the workbench

    window.

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    Problem Faced and Recovery

    Installation problem

    Meshing problem

    Due to some unknown General settings

    Lack of data of boundary condition initially In convergency

    Key of Recovery

    Our group discussion ANSYS tutorials

    useful suggestions of our guide.

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    REFERENCE

    Nuclear Fuel Behavior in Loss-of-coolant Accident (LOCA) Conditions.

    NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION ANDDEVELOPMENT

    Schemes to compute unsteady flashing flows,M. Barret, E. Faucher, J.M. Herard

    Basics of CavitationE.I.P. Drosos, S.V. Paras and A.J. Karabelas.

    Fluid Piping System.Indian Renewable Energy Development Agency,Core 4A, East Court,

    1st Floor, India Habitat Centre,Lodhi Road, New Delhi 110003.

    Basics of Computational Fluid Dynamics.J. Anderson (Jr.)

    Basic aspects of Discritization.

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