Re: FLUKA: Cross section output


To "FLUKA LIST @CERN" <fluka-discuss@listbox.cern.ch>
From Laurent APHECETCHE <aphecetc@in2p3.fr>
Date Thu, 18 Jan 2001 11:39:35 +0100
References <Pine.SOL.4.31.0101171702480.19827-100000@tersk03.SLAC.Stanford.EDU >
Reply-To Laurent APHECETCHE <aphecetc@in2p3.fr>
Sender owner-fluka-discuss@listbox.cern.ch

Hi Alberto,

Thank you very much for your answer.
Indeed, if I understand correctly your mail, it seems impossible from
this output to infer the (total) capture xsec itself, right ?

Actually, I would have another question. Is it possible to investigate
the influence of input neutron libraries, e.g. is it possible to produce
a new set of such input libraries (for selected elements, I think first
of 209Bi in my case) ? How much work would it be for me (is it
feasible/desirable at all ?)

Best regards,

---
Alberto Fasso' wrote:
> Hi,
> I was hoping that somebody else more knowledgeable would answer,
> but since there has been no answer so far, this is the meaning as
> far as I know.
> 
>    Alberto
> 
> ======================================================================
> >  (RESIDUAL NUCLEI INFORMATIONS AVAILABLE)
> 
> This line is self-explaining: for this material it is possible to get
> residual nuclei scoring also from low-energy neutron reactions
> (if you set WHAT(1) = 2.0 or 3.0 in option RESNUCLE). If the line is
> not there for a certain material, only spallation/evaporation residual
> nuclei can be scored.
> 
> >  GROUP
> Energy group number
> 
> >  SIGT
> Total cross section
> 
> > SIGST
> Scattering cross section
> 
> > PNUP
> Probability of upscatter (can be different from zero only if there are
> several thermal groups, which is not the case with the present FLUKA
> cross sections)
> 
> > PNABS
> Probability of Non-ABSorption (= scattering). It is = SIGST/SIGT, and
> can sometimes be > 1 because of (n,xn) reactions
> 
> > GAMGEN
> GAMma GENeration probability = gamma production cross section divided by
> SIGT and multiplied by the average number of gammas per (n,gamma) reaction
> 
> > NU*FIS
> fission neutron production = fission cross section divided by SIGT and
> multiplied by nu, the average number of neutrons per fission
> 
> > EDEP
> Kerma contribution
> 
> > PNEL, PXN, PFISS, PNGAM = partial cross sections, expressed as
> probabilities (i.e. ratios to SIGT). In the order:
>     non-elastic, (n,xn), fission, (n,gamma)
> 
> --
> Alberto Fasso'
> Stanford Linear Accelerator Center
> Radiation Physics Dept. ms 48, 2575 Sand Hill Road, Menlo Park, CA 94025
> Tel. +1 650 926 4062        Fax: +1 650 926 3569
> fasso@slac.stanford.edu     Alberto.Fasso@cern.ch

-- 
Dr. Laurent APHECETCHE (mailto:aphecetc@in2p3.fr) (IN2P3-CNRS) 
SUBATECH-EMN-4 rue Alfred Kastler-BP 20722-44307 NANTES cedex 03
TEL (+33/0) 2 51 85 84 17 - FAX (+33/0) 2 51 85 84 24 (France)
Collaborations PHENIX http://www.phenix.bnl.gov/~aphecetc et MEGAPIE.


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