ch 8 heat transfer

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  • 8/2/2019 Ch 8 Heat Transfer

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    Heat Transfer for a NuclearReactor

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    Review Heat Transfer Terms

    Conduction-occurs across the medium1

    Convection-occurs between a surfaceand a moving fluid

    2

    Radiation Heat Transfer-occursbetween two surfaces

    3

    q kdt

    dx

    q h(Tc Tb )

    q Ts4 T

    sur

    4

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    Heat Generation

    200 MeV/ fission (ER)

    Ed = Energy deposited in locally ~180MeV

    Number of fissions in a core are afunction of the FLUX(f

    FLUX is a function of position in thecore fr,z

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    Heat Generation

    H

    R

    r

    z

    qr(r) 2.32PE

    d

    nERJ0

    2.405r

    R

    qmax 1

    2Ha2qr(0)

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    Decay heat

    Heat is released asthe accumulated

    fission productsdecay

    The amount of heatis fission products to the power level

    P t0,ts P

    P ts P

    P t0 ts

    P

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    Coolant Flow q=w(hout-hin)

    Steam

    Tout

    Water

    Tin

    Tin

    Tout

    q

    q

    Recirculating

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    Plate fuel

    X

    a a+ba

    a+b

    Tfuel Tmax q a2

    2kf

    Tclad Ts x a

    bTs Tc

    q TmaxTc

    a2kfA

    bkcA

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    Cylinder

    z

    Tmax

    Ts

    Tc

    TF

    Tfuel Tmax q r2

    4kf;

    Tclad Ts ln(a b) Tc ln a (Ts Tc )ln r

    ln 1b

    a

    a

    a+b

    q 2Hkc (Ts Tc )

    ln 1b

    a

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  • 8/2/2019 Ch 8 Heat Transfer

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    Coolant Channels

    Now you need toremember more

    heat transfer andfluid mechanics

    The heat transfer fora channel is

    h Ck

    De

    Re

    mPr

    n

    C 0.042P

    D

    0.024

    Re D

    ;Pr

    ;Nu

    hL

    kf

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    Other coolants

    Gas cooled Helium

    Pebble bed in development

    Liquid sodium and potassium

    Need corrosive resistant structure

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    The Boiling Crisis

    ln q

    T

    Annular flow

    Partial film

    Full film

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    LOCA

    Address component breakdown or acombination of component breakdowns

    that lead to interruption of normalcooling

    When an interruption occurs, the fission

    process is terminated, however heatgeneration continues

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    Classifications of operation

    Normal

    Operational transients

    Upsets

    Emergencies

    Limiting Fault Conditions includesDesign basis accident DBA

    Unprotected or beyond DBA

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    Engineered Safety Systems

    The actions aredone as a result of

    instrument signalsReliability

    Duplication

    Diversity

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    Most common ESS

    Alternate cooling

    SCRAM - Tripping - insert control rodsto stop fission

    Control

    Cool

    Contain

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    Some examples

    Millstone 1(660 MWe BWR) - corrosion ofcondensers leads to sea water to enter

    primary cooling circuitBrowns ferry fire -(2 1065 MWe BWR 1 inconstruction) fire affected 2000 cables causeabout $10 M

    Three mile island- relief valve stuck openGinna 490 MWe PWR- rupture in a steamgenerator tube

    Mihama-2 - 500 MWe PWR rupture in a

    steam generator tube

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    More examples

    Chornobyl-Chernobyl

    Chalk River - NRX- control rod/ operator error

    forerunner to the CANDUWindscale fire- UK large air cooled piledesigned for Pu burst fuel cartridge

    St. Laurent - French

    Hunterston scotland - Seawater in the reactorvessel

    Hinckley point

    EBR-1 and Fermi -1 fast breeder.