Hi
If your question is if FLUKA can do some "burn-up" type of calculations, the answer is no. The material definitions are "static" during the run meaning the cross sections are not modified on the "fly" to account for the production of radionuclides.
However FLUKA can use irradiation profile and cooling time to calculate the radionuclides inventory at the end of a given irradiation. You could perform such a calculations to evaluate whether you are producing a sufficient quantities of radionuclides that it would have an impact on the transport of particles....
You can have a look at the manual and at the FLUKA course material on that topic.
https://indico.cern.ch/event/365567/contribution/9/material/slides/0.pdf
Greetings
Joachim
From: owner-fluka-discuss_at_mi.infn.it [mailto:owner-fluka-discuss_at_mi.infn.it] On Behalf Of lzfneu
Sent: 18 May 2015 09:48
To: fluka-discuss_at_fluka.org
Subject: [fluka-discuss]: Question about nuclide density before and after irradiation
dear all,
Can fluka calculate the nuclide density changes of materials before and after irradiation, thanks!
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Received on Mon May 18 2015 - 15:21:07 CEST