From: Sebastien WURTH (firstname.lastname@example.org)
Date: Wed Jan 24 2007 - 12:35:18 CET
1) I don't think there is anything wrong in your input file concerning
your BEAM definition.
When I describe an isotropic source, I can also read the same (about
beam direction cosines) in my *.out file, and my source
is definitely isotropic. You can check it by plotting the fluence
obtained with USRBIN (with usbsuw+pawlevbin+bpawlev or flukagui)
to be sure.
2) You can calculate dose by using USERWEIG card and routine fluscw.f if
you calculate fluence (your case) or comscw.f if you calculate energy
It is explained in the manual, in USRBIN section (note 5), USERWEIG
section and user routines chapter.
You can also calculate dose with a special fluscw routine by Stefan
Roesler (and al) named deq99c.f with USRBIN, USRBDX, USRTRACK (see
several mails in the mailing list in that subject).
Available : dose provided by neutrons, protons, charged pions, muons,
photons and electrons.
Hope it helps.
email@example.com wrote :
>Dear FLUKA users,
>I would like to calculate the dose generated by gamma and neutron.
>The source is isotropic and located at (0, 0, 0).
>My first question is :
>I have specified a WHAT(3)=1.0E+4 in the BEAM card. I have a doubt about the
>output file. It says that the beam direction cosines are 0 0 1: means in the z
> Beam particle: NEUTRON Id: 8 (Fluka) 2112 (PDG) Charge: 0 Baryon n.:
> Mass: 0.9396 (GeV/c^2) Mean life: 888.6 (s) Weight:
> Average beam momentum : 0.097060 (GeV/c)
> Average beam kinetic energy: 0.005000 (GeV)
> Momentum deviation at FWHM (gaussian): 0.0000000 (GeV/c)
> Beam hit position : 0.00000000 0.00000000 0.00000000
> Beam direction cosines: 0.00000000 0.00000000 1.00000000
> Beam spot FWHM X-width (Rectangular ): 0.0000 cm
> Beam spot FWHM Y-width (Rectangular ): 0.0000 cm
> Beam FWHM angular divergence (Rectangular ): ********* (mrad)
> The nominal beam position belongs to region: 1(Reg.#1 ), lattice
>cell: 0( )
>Is there something wrong in my input file?
>The source is surrounded by a Polyethylene container. I would like to
>calculate the dose (Sv/h or Rem/h) coming from gamma and neutrons outside this
>container as a function of the positions.
>First, is it possible to calculate the dose of gamma and neutron ?
>If yes, how can I calculate this values ?
>Thanks in advance
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