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The nuclear cross section of a nucleus is used to describe the probability that a nuclear reaction will occur.^[1]^[2] The concept of a nuclear cross section 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, 10⁻²⁴ cm² or 100 fm². 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 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 ⁠ $\pi r^{2}$ ⁠ or 10⁻²⁸ m² (i.e., 1 barn). Observed cross sections vary enormously: for example, slow neutrons absorbed by the (n, $\gamma$ ) 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 transmutations by gamma-ray absorption are in the region of 0.001 barn.

Microscopic and macroscopic cross section

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:

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

where:

$r_{x}$ : number of reactions of type x, units: [1/time⋅volume]
$\Phi$ : 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 ( $\sigma _{t}=\sigma _{s}+\sigma _{\gamma }+\sigma _{f}+\ldots$ ).

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.

References

^ Younes, Walid; Loveland, Walter (2021). An Introduction to Nuclear Fission. Springer. pp. 10, 25–26, 56–58. ISBN 9783030845940.
^ Rhodes, Richard (1986). The Making of the Atomic Bomb. New York: Simon & Schuster Paperbacks. pp. 333–334, 282–287. ISBN 9781451677614.

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 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.

[ww-1] Younes, Walid; Loveland, Walter (2021). An Introduction to Nuclear Fission. Springer. pp. 10, 25–26, 56–58. ISBN 9783030845940.

[rr-2] Rhodes, Richard (1986). The Making of the Atomic Bomb. New York: Simon & Schuster Paperbacks. pp. 333–334, 282–287. ISBN 9781451677614.

[1]

[2]

@@ Line 1: / Line 1: @@
+{{Short description|Concept in particle physics}}
-The '''nuclear [[cross section (physics)|cross section]]''' of a nucleus is used to characterize the [[probability]] that a nuclear reaction will occur.  The concept of a nuclear cross section 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 (unit)|barn]], which is equal to 10<sup>−28</sup> m² or 10<sup>−24</sup> cm². Cross sections can be measured for all possible interaction processes together, in which case they are called  [[total cross section]]s, or for specific processes, distinguishing [[elastic scattering]] and [[inelastic scattering]]; of the latter, amongst [[neutron cross section]]s the  [[absorption cross section]]s are of particular interest.
+The '''nuclear [[cross section (physics)|cross section]]''' of a nucleus is used to describe the [[probability]] that a nuclear reaction will occur.<ref name="ww">{{cite book |last1=Younes |first1=Walid |last2=Loveland |first2=Walter |title=An Introduction to Nuclear Fission |date=2021 |publisher=Springer |isbn=9783030845940 |pages=10, 25–26, 56–58}}</ref><ref name="rr">{{cite book |last1=Rhodes |first1=Richard |title=The Making of the Atomic Bomb |date=1986 |publisher=Simon & Schuster Paperbacks |location=New York |isbn=9781451677614 |pages=333–334, 282–287}}</ref>   The concept of a nuclear cross section 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 [[Sigma|σ]]) is the [[barn (unit)|barn]], which is equal to {{val|e=-28|u=m2}}, {{val|e=-24|u=cm2}} or {{val|100|u=fm2}}. 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 section]]s the  [[absorption cross section]]s are of particular interest.
-In nuclear physics it is conventional to consider the impinging particles as [[point particle]]s 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<sub>T</sub>.
+In nuclear physics it is conventional to consider the impinging particles as [[point particle]]s 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<sub>T</sub>.
-Typical nuclear radii are of the order 10<sup>−14</sup> m. Assuming spherical shape, we therefore expect the cross sections for nuclear reactions to be of the order of π''r''&thinsp;² or 10<sup>−28</sup> m² (i.e. 1 barn). Observed cross sections vary enormously - for example, [[thermal neutron|slow neutron]]s absorbed by the (n, <math>\gamma</math>) 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 [[Nuclear transmutation|transmutation]]s by [[gamma ray|gamma-ray]] absorption are in the region of 0.001 barn.
+Typical nuclear radii are of the order 10<sup>−15</sup> m. Assuming spherical shape, we therefore expect the cross sections for nuclear reactions to be of the order of {{tmath| \pi r^2}} or {{val|e=-28|u=m2}} (i.e., 1 barn). Observed cross sections vary enormously: for example, [[thermal neutron|slow neutron]]s absorbed by the (n, <math>\gamma</math>) 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 [[Nuclear transmutation|transmutation]]s by [[gamma ray|gamma-ray]] absorption are in the region of 0.001 barn.
-==Macroscopic cross section==
+==Microscopic and macroscopic cross section==
-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]).
+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 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:
+For particle interactions incident upon a thin sheet of material (ideally made of a single [[isotope]]), the nuclear reaction rate equation is written as:
-:<math>r_x = \Phi  \  \sigma_x \ \rho_A = \Phi \Sigma_x </math>
+:<math>r_x = \Phi\ \sigma_x\ \rho_A = \Phi \Sigma_x</math>
 where:
-* <math>r_x</math> : number of reactions of type x, units: [1/time/volume]
+* <math>r_x</math> : number of reactions of type x, units: [1/time&sdot;volume]
-* <math>\Phi</math> : beam flux, units: [1/area/time]
+* <math>\Phi</math> : beam flux, units: [1/area&sdot;time]
-* <math>\sigma_x</math> : microscopic cross section for reaction <math>x</math>, units: [area] (usually [[barn (unit)|barns]] or cm<sup>2</sup>).
+* <math>\sigma_x</math> : ''microscopic'' cross section for reaction <math>x</math>, units: [area] (usually [[barn (unit)|barns]] or cm<sup>2</sup>).
 * <math>\rho_A</math> : density of atoms in the target in units of [1/volume]
-* <math>\Sigma_x \equiv \sigma_x \ \rho_A</math>: macroscopic cross-section [1/length]
+* <math>\Sigma_x \equiv \sigma_x \ \rho_A</math>: ''macroscopic'' cross-section [1/length]
-Types of reactions frequently encountered are ''s'': scattering, <math>\gamma</math>: radiative capture, ''a'': absorption (radiative capture belongs to this type), ''f'': fission, the corresponding notation for cross-sections being: <math>\sigma_s</math>, <math>\sigma_\gamma</math>, <math>\sigma_a</math>, etc. A special case is the total cross-section <math>\sigma_t</math>, which gives the probability of a neutron to undergo any sort of reaction (<math>\sigma_t = \sigma_s + \sigma_\gamma + \sigma_f + ...</math>).
+Types of reactions frequently encountered are ''s'': scattering, <math>\gamma</math>: radiative capture, ''a'': absorption (radiative capture belongs to this type), ''f'': fission, the corresponding notation for cross-sections being: <math>\sigma_s</math>, <math>\sigma_\gamma</math>, <math>\sigma_a</math>, etc. A special case is the total cross-section <math>\sigma_t</math>, which gives the probability of a neutron to undergo any sort of reaction (<math>\sigma_t = \sigma_s + \sigma_\gamma + \sigma_f + \ldots</math>).
-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.
+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.
 ==See also==
@@ Line 29: / Line 30: @@
 ==References==
+{{reflist}}
-{{More footnotes|date=December 2009}}
 * ''Nuclear Reactor Analysis'' by [[James J. Duderstadt]] and [[Louis J. Hamilton]] - ''Published by John Wiley & Sons, Inc.''
 * {{cite book | author=Perkins, Donald H. | title=Introduction to High Energy Physics | publisher=Cambridge University Press | year=1999 | isbn=978-0-521-62196-0}}
@@ Line 35: / Line 36: @@
   | last =Mubarakmand
   | first =Samar
-  | authorlink =Samar Mubarakmand
+  | author-link =Samar Mubarakmand
- |author2=[[Masud Ahmad]] |author3=M. Anwar |author4=M.S. Chaudhry
+ |author2=Masud Ahmad
+ |author2-link=Masud Ahmad
+ |author3=M. Anwar |author4=M.S. Chaudhry
   | title =Cross-section measurements with a neutron generator
   | journal =The Nucleus
@@ Line 48: / Line 51: @@
 [[Category:Scattering]]
+[[Category:Physical quantities]]