Neutron beam hitting Uranium 238 foil

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The discussion focuses on calculating the attenuation of a neutron beam hitting a Uranium-238 foil, along with the rates of elastic reactions and the flux of elastically scattered neutrons. The intensity of the neutron beam is given as 10^6 s^-1, with the foil's density specified at 10^-1 kg m^-2. The elastic and inelastic cross-sections are provided as 1.4 and 2.0 barns, respectively, which are essential for determining the macroscopic cross-section. The formula for attenuation based on the macroscopic cross-section, Σ, is also sought after, highlighting the contributions of both elastic and inelastic interactions. The discussion emphasizes the need to calculate specific outcomes related to elastic scattering from the neutron interactions with the target material.
Steven Brown
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1. Homework Statement [/b]
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.
 
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Given the microscopic cross-section, σ, one should be able to determine the macroscopic cross-section, Σ, with knowledge of the atomic density, N or n.

Then what is the formula for attentuation based on Σ?

Note that one has σi (inelastic) and σe (elastic). Both contribute to attenuation, but parts b and c ask about elastically scattered neutrons.
 
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