Nuclear cross section

The nuclear cross section of a nucleus is used to characterize the probability that a nuclear reaction will occur. The concept of a nuclear cross section is somewhat difficult to conceptualize^{[citation needed]} but can be quantified physically in terms of "characteristic area" where a larger area means a larger probability of interaction. The standard unit for measuring a nuclear cross section (denoted as σ) is the barn, which is equal to 10⁻²⁸ m² or 10⁻²⁴ cm². Cross sections can be measured for all possible interaction processes together, in which case they are called total cross sections, or for specific processes, distinguishing elastic scattering and inelastic scattering; of the latter, amongst neutron cross sections the absorption cross sections are of particular interest.

In nuclear physics it is conventional to consider the impinging particles as point particles having negligible diameter. Cross sections can be computed for any sort of process, such as capture scattering, production of neutrons, etc. In many cases, the number of particles emitted or scattered in nuclear processes is not measured directly; one merely measures the attenuation produced in a parallel beam of incident particles by the interposition of a known thickness of a particular material. The cross section obtained in this way is called the total cross section and is usually denoted by a σ or σ_T.

The typical nuclear radius is of the order of 10⁻¹² cm. We might therefore expect the cross sections for nuclear reactions to be of the order of $\pi r^{2}$ or roughly 10⁻²⁴ cm² and this unit is given its own name, the barn, and is the unit in which cross sections are usually expressed. Actually the observed cross sections vary enormously. Thus for slow neutrons absorbed by the (n, gamma) reaction the cross section in some cases is as much as 1,000 barns, while the cross sections for transmutations by gamma-ray absorption are in the neighborhood of 0.001 barns.

Nuclear cross sections are used in determining the nuclear reaction rate, and are governed by the reaction rate equation for a particular set of particles (usually viewed as a "beam and target" thought experiment where one particle or nucleus is the "target" [typically at rest] and the other is treated as a "beam" [projectile with a given energy]).

For neutron interactions incident upon a thin sheet of material (ideally made of a single type of isotope), the nuclear reaction rate equation is written as:

r_{x}=\Phi \ \sigma _{x}\ \rho _{A}=\Phi \Sigma _{x}

where:

$r_{x}$ : number of reactions of type x, units: [1/time/volume]
$\Phi$ : neutron beam flux, units: [1/area/time]
$\sigma _{x}$ : microscopic cross section for reaction $x$ , units: [area] (usually barns or cm²).
$\rho _{A}$ : density of atoms in the target in units of [1/volume]
$\Sigma _{x}\equiv \sigma _{x}\ \rho _{A}$ : macroscopic cross-section [1/length]

Types of reactions frequently encountered are s: scattering, $\gamma$ : radiative capture, a: absorption (radiative capture belongs to this type), f: fission, the corresponding notation for cross-sections being: $\sigma _{s}$ , $\sigma _{\gamma }$ , $\sigma _{a}$ , etc. A special case is the total cross-section $\sigma _{t}$ , which gives the probability of a neutron to undergo any sort of reaction ( $\sigma _{t}=\sigma _{s}+\sigma _{\gamma }+\sigma _{f}+...$ ).

Formally, the equation above defines the macroscopic neutron cross-section (for reaction x) as the proportionality constant between a neutron flux incident on a (thin) piece of material and the number of reactions that occur (per unit volume) in that material. The distinction between macroscopic and microscopic cross-section is that the former is a property of a specific lump of material (with its density), while the latter is an intrinsic property of a type of nuclei.

References

Nuclear Reactor Analysis by James J. Duderstadt and Louis J. Hamilton - Published by John Wiley & Sons, Inc.
Perkins, Donald H. (1999). Introduction to High Energy Physics. Cambridge University Press. ISBN 0-521-62196-8.

See also

References