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Forum: Geometry
Re: Question Element definition (Steve Quillin)
Date: 09 Jul, 2015
From: michel maire <michel maire>

On Tue, 07 Jul 2015 18:57:25 GMT, Steve Quillin wrote:
> Hello
> 
> I'm trying to simulate some publicised data on spallation and have made
> a simple Geant4 application that fires 1 GeV protons into a 10 cm
> uranium sphere and counts the numbers of neutrons emitted. My problem is
> with the material definition: results seem to be dependant on the order
> in which I add isotopes to an element.
> 
> My material definitions and the results of "printing" them are attached
> below. All 3 materials appear identical apart from the isotope order,
> yet the neutron multiplicity is smaller by a factor of ~2 (geometry
> dependant) when the target sphere is built from Uranium_b than the
> others. The fraction of protons that generate neutrons is the same for
> all materials.
> 
> Have I made an error in the material definitions or is there something
> else going on?
> 
> I'm using geant4-10-01-patch-01 multithreaded with QGSP_BIC and other
> physics lists.
> 

  I ran example Hadr03 with the 2 Uranium definitions.
  I attach macro and extract of outputs (which are big, at 1 GeV)
  The number of generated neutrons are close, althrough not exactly the same.
  (spectrum in attachment)

  I do not know how much is signifiant this difference of behaviour between the 2 material definitions.

   Attachment:
      http://hypernews.slac.stanford.edu/HyperNews/geant4/get/AUX/2015/07/09/07.05-5690-quillin.mac.txt
      http://hypernews.slac.stanford.edu/HyperNews/geant4/get/AUX/2015/07/09/07.05-97750-u_nist.out.txt
      http://hypernews.slac.stanford.edu/HyperNews/geant4/get/AUX/2015/07/09/07.05-77337-u_b.out.txt
      http://hypernews.slac.stanford.edu/HyperNews/geant4/get/AUX/2015/07/09/07.05-16262-uranium.gif

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