|Message: Re: Problem with G4PSCellFlux||Not Logged In (login)|
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Thank you for your quick answer. My geometry is an aluminum cylinder (internal radius = 36 mm, external radius = 38.25 mm and length = 702.5 mm) which contains three other smaller cylinders (internal radius = 11.5 mm, external radius = 12.7 mm and length = 566 mm). The three smaller cylinders have a thin thickness of boron (1.26 um). I have a simple source of thermal neutrons and I want to compare the (n, alpha) reaction rate and neutron flux in the boron thickness with MCNP.
To calculate the reaction rate in the boron with G4, I use this simple definition: Reaction rate = number of (n, alpha) / number of particles simulated. With MCNP I found the same result of reaction rate. But the result of the flux in one boron cylinder is different.
I checked the track-length with G4PSTrackLength scorer as you said me and the problem is not the calculation of the cell volume.
Maybe the problem is with my PhysicList, I only use QGSP_BERT_HP physicList. Should I create my physicList for thermal neutrons ?
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