Neutron beam hitting Uranium 238 foil

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SUMMARY

The discussion focuses on calculating the attenuation of a neutron beam passing through a Uranium-238 foil. The neutron beam has an intensity of 106 s-1, and the foil has a density of 10-1 kg m-2. The elastic and inelastic cross-sections are given as 1.4 b and 2.0 b, respectively. Key calculations include the attenuation of the beam, the rate of elastic reactions, and the flux of elastically scattered neutrons at a distance of 5 m from the target.

PREREQUISITES
  • Understanding of neutron beam physics
  • Familiarity with cross-section terminology
  • Knowledge of flux and reaction rate equations
  • Basic integration techniques in physics
NEXT STEPS
  • Study neutron interaction cross-sections in detail
  • Learn about the principles of neutron flux calculations
  • Explore the concept of elastic vs. inelastic scattering
  • Review integration techniques for physics applications
USEFUL FOR

Students and researchers in nuclear physics, particularly those studying neutron interactions and scattering processes. This discussion is also beneficial for anyone involved in experimental physics or radiation detection methodologies.

Steven Brown
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Homework Statement


A high energy beam of neutrons of intensity 10^6 s^-1 transverses a target of 238 U of thin foil whose density per unit area is 10^-1 kg m^-2. If the elastic and in elastic cross-sections are 1.4 and 2.0 b, respectively, calculate(a) the attenuation of the beam(b) the rate of elastic reactions and(C) the flux of elastically scattered neutrons 5 m from the target, averaged over all scattering angles.

Homework Equations



flux J=NbVi
Wr=jNsigma, r
The reduction in beam intensity on crossing the segment is is equal to the reaction rate dW within the segment
AdJ(x)=-dW
dW=j(x)sigma nt Adx

The Attempt at a Solution

 
Last edited:
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tried integrating over the input Ji exp (-x/ln)sigma nt Adx and I am totally stumped
 

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