Re: [fluka-discuss]: Source.f user routine for neutrons

From: Konstantin Batkov <batkov_at_gmail.com>
Date: Fri, 2 Aug 2024 09:43:04 +0200

Hi Beatrice,

See the User-defined sources section in this lecture:
https://agenda.infn.it/event/20624/contributions/105889/attachments/68617/84988/AdvancedSources2019.pdf

However, you can define such a source without modifying source.f by
creating a BEAMSPOT special source as shown in the attached file (note that
I have reversed your beam direction - otherwise, it would never reach the
wall).

> is it correct to use the BEAM card as NEUTRON with a generic energy level
of 100MeV, as the maximum energy expected in the current run, before
recalling the SOURCE card?

Yes, in this case that energy sets the maximal energy for cross section
tabulation, so it should exceed the energies of your incident particles.

Konstantin



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Received on Fri Aug 02 2024 - 12:26:57 CEST

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