pdf 3.3 one-on-one probabilities-neutron vs nuclide

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  • 7/28/2019 PDF 3.3 One-On-One Probabilities-Neutron vs Nuclide

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    Nuclear Reactionsand Radiation

    3.3 One-on-One Probabilities

    Neutron versus Nuclide;

    Some neutrons are better thanothers

    L. R. Foulke

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    Nuclear Reaction Rates So far we have covered:

    Atomic / nuclear structure Nuclear stability Types of radioactive decay / radiation Radiation interactions Neutron interactions

    Remaining question: How can we predict the expected frequency of neutron

    interactions in a medium? A substance such as nuclear fuel?

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    Probability of an Interaction We start by considering theprobability that a neutron

    will strike a single nucleus

    Assume that the neutron andnucleus are both solid

    spheres.

    The neutron sees thenucleus as a round target with

    area:A = r2 where ris theradius of the nucleus.

    Probability of interaction isproportional to cross sectional

    area of nucleus.

    Atom

    Free Neutron

    Top View Neutron View

    (Side View)

    Image Source: See Note 1

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    Probability of an Interaction A reaction will occur whenany part of the neutron

    contacts the nucleus

    May be straight-on or glancingblow.

    This increases the effectivetarget area of the nucleus by

    the radius of the neutron, rn.

    The effective target area ofthe nucleus is referred to as

    the microscopic cross

    section for the nuclide.Atom

    Free Neutron

    Top View Neutrons View

    (Side View)

    EffectiveTarget Area

    EffectiveTarget Area

    miss

    Image Source: See Note 1

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    Microscopic Cross Section Microscopic cross section

    Cross sectional area of nucleus as seen by neutron, denotedby symbol (units of cm2/nucleus)

    Has units of area, given in units ofbarns 1 barn = 1024 cm2

    Proportional to the probability that a neutron will strike thenucleus and undergo a reaction

    Nuclide dependent Seems like it should be proportional to the nuclear

    radius

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    Microscopic Cross SectionMicroscopic Cross Sections Calculated vs. MeasuredNeutron radius: rn=0.8510

    15 [meters]

    Nuclear radius: ra=1.21015 (A)1/3[meters] (A is atomic mass)

    Theoretical Microscopic Cross Section: =(rn+r

    a)2[meters2]

    Nuclide Calculated Measured

    1H 0.132 barns 20.43 barns4He 0.238 barns 0.759 barns235

    U 2.140 barns ~500 barns

    Theoretical (solid spheres) model is correct to within a couple oforders or magnitude, but it is not a good approximation

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    Microscopic Cross Sections

    Nuclide Calculated Measured* @ incident energy of 0.1 eV

    1H 0.132 barns 20.43 barns4He 0.238 barns 0.759 barns235U 2.140 barns ~500 barns

    U-235

    He-4

    H-1

    Total microscopic cross sections as a function of

    incident neutron energy

    Image Source: See Note 1

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    Microscopic Cross Section In reality quantum effects play a large role in determining the effective

    target area of the nucleus as seen by an approaching neutron

    The microscopic cross section depends heavily on: The structure / stability of the target nucleus

    Partially filled neutron shells are more receptive to a neutroninteraction than completely filled shells

    The energy of the neutron

    Typically low-energy (slow) neutrons are more likely to interactwith a nucleus than high-energy (fast) neutrons.

    The neutron energy dependence is extremely complicated

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    Microscopic Cross Section

    Image Source: See Note 2

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    Microscopic Cross Section The energy dependence of microscopic cross sections can bedivided into three ranges:

    High Energy (neutron energy > 1 keV) (aka FAST range) Quantum effects are less important and probability of

    interaction shows little variation. Resonance Range (1 eV < neutron energy < 1 keV)

    Quantum effects dominate and probability of interactiondepends on how closely the neutron energy matches an

    unfilled nuclear shell in the target nuclide.

    Thermal / 1-over-v Range (neutron energy < 1 eV) Probability of interaction increases as neutron energy

    (velocity) decreases

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    Microscopic Cross Section

    1/v Range(Thermal range)

    ResonanceRange

    High-Energy

    Range(Fast range)

    Image Source: See Note 2

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    Analogy for

    1-over-vNeutron

    Absorption

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    1 MeV

    235U

    238

    U

    Uranium Fission Cross Sections

    Image Source: See Note 2

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    Uranium-235 Fission Cross Section

    235U

    1 barn0.025 eV

    584 barns

    10 MeV0.1 Mev

    Thermal Advantage~ x500+

    Image Source: See Note 2

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    1. Reprinted with permission from DavidGriesheimer, University of Pittsburgh.

    2. Adapted with permission from the AmericanNuclear Society. Nuclear Engineering Theory and Technology of CommercialNuclear Powerby Ronald Allen Knief, 2nd

    Edition. Copyright 2008 by the AmericanNuclear Society, La Grange Park, Illinois.Figure 2-12 (slides 9, 11, 13, and 14).

    Image Source Notes