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    Six Factor Formula

    (Reactor Physics)

    Presented by:Seraj ul Haq, PE

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    Contents

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    Revision

    Fast Neutrons, Thermal Neutrons?

    Fission?

    Fast, Thermal Cross-section?

    Resonance? Resonance Peaks?

    Probability? Sun will set today: Probability =? [0, +0.x, >1]

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    Multiplication Factor k

    k =

    k < 1, Dieing reaction k = 1, Sustained reaction k > 1, Increasing (uncontrollable?) reaction

    k = 0 (??), k < 0 (???)

    Neutron production from fission in one generation

    Neutron absorption in the preceding generation

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    Fast Fission Factor,

    =

    Cross section of fast fission is small Also effected by fuel and Mod arrangement Normally 1 in homo, b/c fuel atoms surrounded by mod 1.03 in hetro

    T, P, Enrichment, poisons effect ???

    Number of fast neutrons produced by all fissions

    Number of fast neutrons produced by thermal fissions

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    Resonance Escape Probability, p

    p =Number of fast neutrons that reach thermal energy

    Number of fast neutrons that start slow down

    Resonance range for U-238 is 6 eV 200 eV

    In homo, p is small compared to hetro (why ?)

    p mainly effected by fuel temp due to Doppler effect (?), mod tempdue to change in density (?)

    Will poison effect?

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    Thermal Utilization Factor, f

    f =

    Effected by change in T, not directly but due to moderator inventory

    (How?)Poison (How?), Enrichment (?)

    Value always < 1 (?)

    Number of thermal neutrons absorbed in fuel

    Number of thermal neutrons absorbed in all Rx materials

    p

    a

    m

    a

    U

    a

    U

    a

    ppp

    a

    mmm

    a

    UUU

    a

    UUU

    a

    VVV

    V

    p

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    Reproduction Factor,

    =Number of fast neutrons produced by all fissions

    Number of fast neutrons produced by thermal fissions

    Will Temp effect (How?)

    Poison (How?), Enrichment (?)

    Value always < 1 (?)

    238238235235

    235235235

    aa

    f

    UU

    a

    UU

    f

    NN

    N

    Single nucleus

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    Multiplication Factor k

    k =

    Supposed all neutrons remain within the assembly

    Neutron production from fission in one generation

    Neutron absorption in the preceding generation

    fpk

    Four factor formula

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    Effective Multiplication Factor

    kef =Neutron production from fission in one generation

    Neutron absorption in thepreceding generation

    Will Four factor formula work?

    Neutron Leaked in thepreceding generation+

    Neutron production from fission in one generation

    Neutron production from all fissions in preceding generation (?)kef =

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    Fast Non-Leakage Probability, Lf

    L =Number of fast neutrons that do not leak off from the Rx

    Number of fast neutrons produced by all fissions

    Always less than 1 in practical Rx?

    Will Temp. effect?

    Will Geometry effect

    f

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    Thermal Non-Leakage Probability, Lt

    L =Number of thermal neutrons that do not leak off from the Rx

    Number of neutrons that reach thermal energies

    Always less than 1 in practical Rx?

    Will Temp. effect?

    Will Geometry effect

    t

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    Effective Multiplication Factor

    k = Neutron production from fission in one generation

    Neutron absorption in the preceding generation

    tfLLfpk

    Six factor formula

    eff

    eff

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    Neutrons in the nth Generation

    Knowing the value of Keff, we can find

    Where

    Nn neutrons in nth generation

    N0 neutrons in firstgeneration

    n

    eff0n )(kNN

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    Critical, Sub/Super Critical

    If Keff = 1, Rx is Critical

    Can be critical at any power value

    Remember, power doesn't depend upon k

    For Keff < 1, Rx is Sub-Critical For Keff > 1, Rx is Super-Critical

    How can we increase or decrease Keff of apractical reactor? Think!

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    SixFactorFo

    rmula

    (Explanation)

    140 FAST NEUTRONS LEAK OUT

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    NOpLf

    100 THERMALNEUTRONS LEAK

    OUT FROM THE

    CORE

    180

    NEUTRONS

    ABSORBED

    BY

    RESONAN

    CE PEAKSFAST

    FISSION

    = 1.04

    FAST

    NON-

    LEAKAGE

    Lf= 0.865

    RESONAN

    CE

    ESCAPE

    p = 0.80

    THERAM

    NON-

    LEAKAGE

    Lt = 0.881

    THERMA

    UTILIZATIO

    N

    f = 0.799

    REPRODUCATION

    = 2.02

    1000 NEUTRONS AT START OF

    GENERATION

    NET INCREASE OF

    40 NEUTRONS

    FROM FAST

    FISSION

    NO

    NO

    1040

    NEUTRONS

    140 FAST NEUTRONS LEAK OUT

    FROM THE CORE

    900NEUTRONS

    NOLf

    720

    NEUTRONS

    620

    NEUTRONS

    NOpLfLt

    120 NEUTRONS ABSORBED IN

    NON FUEL

    495

    NEUTRONS

    NOpLfLtf

    NET INCREASE OF 505

    NEUTRONS FROM

    THERMAL FISSION

    1000 NEUTRONS

    k NO

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    Reactivity, The gain or loss in neutron population (N0keff N0),

    expressed as a fraction of the present generation (N0keff)

    Fractional variation of keff from 1

    eff0

    0eff0

    kN

    NkN

    eff

    eff

    k

    1k

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    Reactivity, Reactivity () could be 0,

    >0 or

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    Units of Reactivity,

    A friction; dimensionless

    Can be expressed as simple

    fraction, percent Some times expressed as

    pcm (Percent milli) = 10-5

    Dollar ($) [reactivity when Rx is

    prompt critical; = 0.0068

    k

    1k

    k

    k

    k

    k

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    For Tomorrow

    1. Reactivity Coefficients

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    Thank you for your attention