Re: [fluka-discuss]: Interpretation of cross section and yield from USRYIELD

From: Alberto Fasso' <fasso_at_slac.stanford.edu>
Date: Wed, 22 Jan 2014 06:19:36 -0800 (PST)

Dear Lee,

you get a big output file because you are using the default version of
MGDRAW. It is better to follow the instructions below (that you find also in
the manual description of USERDUMP):

     The default version of the routine writes a complete dump (unformatted) of
     one or more of the following:
                      - all source particles
                      - all particle trajectories
                      - all local (pointlike) energy deposition events
                      - all continuous energy deposition events
                      - user-defined events
     Users can modify the routine by removing the existing lines of code and by
     writing their own code under one or more of the entries.

That's it: remove all the lines of code (except the INCLUDE statements at the
beginning) and open your own files and write your own logics under the
ENTRYes you are interested in.

In a similar way,

          WHAT(2) : if the default version of MGDRAW is used, ....
                    ... forget this

                    if a user version is used: ...
                    ... follow these instructions for the user version

Alberto


On Sat, 18 Jan 2014, Chenyen Lee wrote:

> Dear Anton and Forum :
>
> Pardon me, I would like to ask a very elementary question.
> I do not know how to use the USDRAW in the MGDRAW to modify to as Anton's
> instuction.
> I add the USERDUMP, but just get a big output file of DUMP.
> I find the mgdraw.f file but do not know how to do it correctly.
>
> I read the manual and the UserRoutines.pdf
> www.fluka.org/content/course/NEA/.../UserRoutines.pdf
> Is there any more elementary documents or instructions?
>
> Thanks in advance
>
> Lee
>
>
>
>
> 2013/11/30 Anton Lechner <Anton.Lechner_at_cern.ch>
> Dear Lee,
>
> You can interpret the values you specify (from the summary file
> created with USYSUW) as follows: for example, the differential
> yield of 0.1 GeV^-1 you get in the energy interval 0-0.01 GeV
> simply means that 0.1 GeV^-1*0.01GeV=1E-03 neutrons with E<10
> MeV were produced in inelastic hadronic interactions within
> your entire geometry (also in the surrounding air). Of course
> this is consistent with the value you got for the larger energy
> interval, since most neutrons are below 10 MeV.
>
> From the link you included in your file, I guess that you are
> only interested in neutrons produced in following reaction:
> p + O18 -> F18 + n
>
> If this is the case, you should not forget that a
> non-negligible fraction of neutrons also emerge from other
> processes, e.g.:
> p + O18 -> O17 + n + p
> p + O18 -> N14 + n + alpha
>
> USRYIELD will count all neutrons, also those from the latter
> interactions.
>
> If you are only interested in the first reaction, you could for
> example use USDRAW in the MGDRAW user routine. By including
> '(RESNUC)', you have access to the atomic and mass number of
> the residual nucleus and you can filter neutrons accordingly. I
> included some sample code below.
>
> Cheers, Anton
>
>
> * Check that incoming particle is a proton and that interaction
> is inelastic:
>       IF ( JTRACK .EQ. 1 .AND. ICODE .EQ. 101 ) THEN
>
> * Check that residual nucleus is F18: 
>          IF( ICRES .EQ.9 .AND. IBRES .EQ.18 ) THEN
>
> * Loop over all secondaries
>              DO 99 INMB = 1, NP
>
> * Check that secondary particle is a neutron
>                 IF ( KPART( INMB ) .EQ. 8 ) THEN
>  * Here you might want to write to a file e.g. the neutron
> energy  TKI (INMB ) or simply count neutrons
>                 ENDIF
>
>  99        CONTINUE
>
>         ENDIF
>       ENDIF
>
>
>  
> Thanks in advance
>
>
> Lee
>
>
> --
> 03-3281200-3591
> 0972164977
> Chenyen Lee
> Department of Nuclear Medicine
> Chang Gang Memorial Hospital
> Linko,Taiwan
>
>
>
>

-- 
Alberto Fasso`
SLAC-RP, MS 48, 2575 Sand Hill Road, Menlo Park CA 94025
Phone: (1 650) 926 4762   Fax: (1 650) 926 3569
fasso_at_slac.stanford.edu
Received on Wed Jan 22 2014 - 16:35:21 CET

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