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Nuclear cross section

In nuclear physics it is conventional to consider the impinging particles as point particles having negligible diameter. Cross sections can be computed for any nuclear process, such as capture scattering, production of neutrons, or nuclear fusion. 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.

Typical nuclear radii are of the order 10⁻¹⁵ m. Assuming spherical shape, we therefore expect the cross sections for nuclear reactions to be of the order of ⁠${\displaystyle \pi r^{2}}$⁠or10⁻²⁸ m² (i.e., 1 barn). Observed cross sections vary enormously: for example, slow neutrons absorbed by the (n, ${\displaystyle \gamma }$) reaction show a cross section much higher than 1,000 barns in some cases (boron-10, cadmium-113, and xenon-135), while the cross sections for transmutationsbygamma-ray absorption are in the region of 0.001 barn.

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", which is typically at rest, and the other is treated as a "beam", which is a projectile with a given energy).

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

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

where:

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

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

Formally, the equation above defines the macroscopic cross-section (for reaction x) as the proportionality constant between a particle 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.

• Neutron cross-section
• Scattering cross-section

• Nuclear Reactor AnalysisbyJames 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 978-0-521-62196-0.
• Mubarakmand, Samar; Masud Ahmad; M. Anwar; M.S. Chaudhry (1977). "Cross-section measurements with a neutron generator". The Nucleus. 42 (1–2). Nilore, Islamabad: PINSTECH: 115–185.