Hi Saneesh,
1.
> How will I get an energy spectrum of neutrons with 0.25
> MeV or 0.5 MeV bin width which is uniform?
no way, neutrons below 20 MeV are treated by a multigroup algorithm with a
pre-defined binning, as made clear in the manual.
2.
> The unit of flux is given in the sum.lis output as Flux
> (Part/sr/GeV/cmq/pr).
No need to redo the integrations yourself, in the sum.lis output you find
also the total response as
Tot. resp. (Part/cmq/pr)
as well as (Part/pr)
In addition, you get there also the cumulative fluence/current, integrated
from the upper energy limit down to any intermediate energy value.
Pay attention to the difference between fluence and current.
Kind regards
Francesco
**************************************************
Francesco Cerutti
CERN-EN/STI
CH-1211 Geneva 23
Switzerland
tel. +41 22 7678962
fax +41 22 7668854
On Tue, 26 Sep 2017, Saneesh N wrote:
>
>
> ____________________________________________________________________________________
> From: "Saneesh N" <saneesh_at_iuac.res.in>
> To: "fluka-discuss" <fluka-discuss_at_fluka.org>
> Sent: Monday, September 25, 2017 5:53:12 PM
> Subject: Bin size
>
> Dear FLUKA experts,
>
> I am using 'source.f' for generating Maxwellian energy distribution for neutrons
> (energy ranging from 0.0 to 10 MeV). Here I am facing two problems,
>
> 1. The energy distribution using USRBDX card shows non- linear energy binning,
> smaller bin for lower energies and bigger energy bin for higher energies (The image
> file is attached). Even though I have changed the value of energy bin in the USRBDX
> card, there was no change. How will I get an energy spectrum of neutrons with 0.25
> MeV or 0.5 MeV bin width which is uniform?
>
> 2. How to cross-check the number of events reaching a material medium using USRBDX
> output? The unit of flux is given in the sum.lis output as Flux
> (Part/sr/GeV/cmq/pr). To get the number of particles, I have multiplied Flux with
> solid angle (2*PI), centre value of energy bin, area of the detector (78.539) and
> incident primary (1.E5). And then summed over all energy points. But the result was
> not coming as 1.E5. When I have counted the neutron fluence event by event using
> EVENTBIN card, it was coming to be 1.E5. So how to do similar validation using
> USRBDX card.
>
> Kindly help me to solve these problems. The input file, source file and the image
> files are attached.
>
>
> Thanks in advance
>
> Saneesh N
>
> IUAC, New Delhi
>
>
>
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Received on Tue Sep 26 2017 - 17:48:18 CEST