Dear Sir,
Thank for your information. In fact, i just want to avoid to do my all
simulation at the same time (my simulation calculate the neutron activation
due to neutron production by heavy ion collission) so i can reduce the time
of calculation by using the two steps method like Mr Polkovnikov say. I
prefer the built-in method in FLUKA too to avoid some possibles mistakes
like you say.
Best regards.
2015-06-02 21:56 GMT+02:00 Joachim Vollaire <joachim.vollaire_at_cern.ch>:
> Hi
>
> Maybe to complement Mikhail suggestions. If you have the energy dependant
> neutron spectra information, you can fold the spectra to radionuclides
> production cross sections. If you consider, all production channels in the
> concerned material (reactions on different target nuclei leading to the
> same produced isotopes) and associated atomic density of the target nuclei
> you can calculate the production yield for the concerned isotopes.
>
> Now if you want to score the radionuclides inventory for a given
> irradiation pattern and cooling time, you need to resolve the Bateman
> equations looking at the decay scheme of each produced radionuclides
> determined with the previous method. Consider that some radionuclides can
> be produced by decay of several radionuclides…. You can use the WHAT(4) of
> the LOW-NEUT card with maximum details printed to have information on the
> produced radionuclides by low energy neutrons in your material (it will
> create big .out file so do it for a single run) ….
>
>
>
> So as you can see both the production yield calculations and resolution of
> the Bateman equation requires a lot of post-processing, thus I would
> strongly recommend using the built-in method available in FLUKA to avoid
> mistakes. I would only do it “manually” for radionuclides produced on
> traces for which the statistics may not be sufficient with the built-in
> method….
>
> Hoping this help
>
> Joachim
>
>
>
>
>
>
>
> *From:* owner-fluka-discuss_at_mi.infn.it [mailto:
> owner-fluka-discuss_at_mi.infn.it] *On Behalf Of *"Mikhail Polkovnikov
> <?????? ???????????>"
> *Sent:* 02 June 2015 15:26
> *To:* Ngoc-Duy Trinh; fluka-discuss_at_fluka.org
> *Subject:* Re: [fluka-discuss]: Neutron activation in Fluka
>
>
>
> On 02.06.2015 10:46, Ngoc-Duy Trinh wrote:
>
> Dear FLUKA users,
>
>
>
> I want to calculate the residual nucleides due to neutron activation with
> a given neutron spectra in 260 groups calculated before by another FLUKA
> simulation ? I dont want to put all my simulation in the same time to
> reduce the time of calculation, so i want to know is it possible to
> calculate like this ? and how can i do it ?
>
>
>
>
>
> Best regards.
>
>
>
> --
>
> TRINH Ngoc Duy
>
> Stagiaire - Service de Physique - Grand accélérateur national d'ions
> lourds
>
> Master 2 Instrumentation nucléaire - Université de Bordeaux
>
> ndtrinh_at_outlook.fr - trinhngocduy.k55_at_hus.edu.vn - ngoc-duy.trinh_at_ganil.fr
>
> Tél : 0783188922
>
> Dear Ngoc-Duy Trinh,
>
> There are two ways.
>
> The first one is to use the "two-step methods" as described in
> https://indico.cern.ch/event/334606/contribution/35/material/slides/0.pdf
> (slides 43-49). The second one is to sample a given neutron spectrum into
> SOURCE routine within a new geometry (which is a part of the whole
> simulation).
>
> In both cases you have to use SOURCE routine, but the second approach
> might be much easier.
>
> Best regards.
>
--
TRINH Ngoc Duy
Stagiaire - Service de Physique - Grand accélérateur national d'ions lourds
Master 2 Instrumentation nucléaire - Université de Bordeaux
ndtrinh_at_outlook.fr - trinhngocduy.k55_at_hus.edu.vn - ngoc-duy.trinh_at_ganil.fr
Tél : 0783188922
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Received on Wed Jun 03 2015 - 10:44:31 CEST