The difference between microscopic and macroscopic cross sections.

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SUMMARY

This discussion focuses on the comparison of microscopic and macroscopic cross sections, specifically for the elements B, Cd, Gd, and Hf relative to the fission cross section of U-235. Microscopic cross sections (σ) are measured in barns, representing the effective area for nuclear reactions, while macroscopic cross sections (Σ) are calculated using the formula Σ = N σ, where N is the atomic density. The reaction rate for a given interaction is expressed as Σ Φ, with Φ representing neutron flux. These concepts are essential for understanding neutron interactions in nuclear physics.

PREREQUISITES
  • Understanding of nuclear physics concepts, particularly cross sections
  • Familiarity with the periodic table and atomic density calculations
  • Knowledge of neutron flux and its significance in nuclear reactions
  • Basic mathematical skills for applying formulas and integrals
NEXT STEPS
  • Research the specific microscopic absorption cross sections for B, Cd, Gd, and Hf
  • Study the fission cross section of U-235 in detail
  • Learn about neutron flux and its measurement techniques
  • Explore integral calculus applications in nuclear physics for varying energy spectra
USEFUL FOR

Students and professionals in nuclear physics, nuclear engineers, and researchers focusing on neutron interactions and reactor physics will benefit from this discussion.

CaptainMayhem
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Hello there folks. So I'm doing some homework, and one of the questions asks for a comparison of the microscopic absorption cross sections of B, Cd, Gd, and Hf with the fission cross section of U-235. I've found the fission cross section in my trusty 17th edition of Nuclides and Isotopes, but the next part of the question confused me. It then asks for the macroscopic cross sections assuming density is derived from the periodic table.

I'm not sure how to figure out the micro/macroscopic cross sections. There is only one given value per nuclide. Help?!
 
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Microscopic cross-sections (σ) are given for each nuclide usually in units of barns, where 1 b = 1 x 10-24 cm2. It is essentially the effective area for the particular reaction.

The macroscopic cross-section (Σ) has units of cm-1 is derived from the microscopic section according to

Σ = N σ, where N is the atomic density of a particular nuclide.

The reaction rate for a give interaction = Σ Φ, where Φ is the neutron flux.

These formula work well for average or thermal neutron energies. If a wide enough energy spectrum is considered then one has to use integrals over the appropriate energy range.
 

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