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Neutron beam hitting Uranium 238 foil

  1. Apr 5, 2009 #1
    1. The problem statement, all variables and given/known data
    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.


    2. Relevant 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

    3. The attempt at a solution
     
    Last edited: Apr 5, 2009
  2. jcsd
  3. Apr 5, 2009 #2
    tried integrating over the input Ji exp (-x/ln)sigma nt Adx and im totally stumped
     
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