Absorption Cross Section & Irradiation: Explained

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SUMMARY

The discussion clarifies the concepts of absorption cross section and irradiation within the context of nuclear engineering. The absorption cross section quantifies the probability of a neutron being absorbed by a nucleus, with units of length squared. It is integral to the 1D linear attenuation equation, where the macroscopic cross section, derived from the microscopic cross section and the number density, represents a material property. Irradiation refers to the exposure of materials to various forms of radiation, including neutrons and x-rays.

PREREQUISITES
  • Nuclear engineering principles
  • Understanding of cross section terminology
  • Familiarity with the 1D linear attenuation equation
  • Knowledge of radiation types (neutrons, beta particles, x-rays)
NEXT STEPS
  • Study the derivation and applications of the 1D linear attenuation equation
  • Explore the differences between microscopic and macroscopic cross sections
  • Investigate various types of radiation and their effects on materials
  • Learn about neutron interaction probabilities in nuclear reactions
USEFUL FOR

Nuclear engineers, radiation safety professionals, and students studying nuclear physics will benefit from this discussion, particularly those interested in the quantitative aspects of nuclear interactions and material irradiation processes.

Chuckmaster
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Can someone explain what absorption cross section is and how it's figured into an equation? And what is irradiation?
 
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The cross section is conceptually the area a nucleus presents to a target, having units of length squared. You can interpret this as roughly the relative probability of a nuclear intereaction occurring. Things with a high cross section have a much higher likelyhood than things with a low one.

Every kind of nuclear reaction has a cross section. An absorption cross section in most nuclear engineering roughly describes the probability of a neutron (or other particle) being absorbed by a nucleus.

An equation where this often shows up is in the 1D linear attenuation equation. The cross section (sigma) is usually referred to as a microscopic cross section as it is independent of material properties. The macroscopic cross section (capital sigma or sometimes mu) is the product of the number density A (units of m^-3) and the microscopic cross section (units of m^2) giving units of inverse length (m^-1). The macroscopic cross section is useful because it is a material property.

Say you have a beam of neutrons of intensity I0 incident on a thick slab of material. When the beam strikes the material, it will penetrate and some of the neutrons will be absorbed. The intensity of the beam at any point in the material is given as:

I(x) = I0*exp(-(macroscopic cross section)*x)

Where:

I(x) = beam intensity at position x
I0 = beam intensity at surface of target
x = distance in target.

Irradiation is the process of subjecting a material to some kind of radiation whether it be neutrons, beta particles, x-rays, microwaves, etc.
 

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