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Using Input Macroscopic Cross Section Libraries

Posted: Tue Feb 23, 2021 6:10 pm
by PRoux
Serpent users and developers

I was wondering if it was possible to use a macroscopic cross section library as an input in a Serpent input?
So basically, instead of using the ACELIBS, is it possible to provide a path to a macroscopic library? If so, is there a specific format?

Thanks !

Re: Using Input Macroscopic Cross Section Libraries

Posted: Tue Feb 23, 2021 7:06 pm
by Ana Jambrina
There is no such option.
Alternatively, maybe an option would be to replicate the ACE formatted libraries used by Serpent based on the macroscopic cross-section data (for additional ACE-format info, check MCNP manual - appendices).

Re: Using Input Macroscopic Cross Section Libraries

Posted: Tue Feb 23, 2021 7:06 pm
by Jaakko Leppänen
Unfortunately, no. The transport simulation operates on microscopic level, and in addition to reaction probabilities (characterized by cross sections) the data includes energy and angular distributions that describe the scattering physics of individual neutron-target interactions. The connection to macroscopic cross sections (used for the deterministic solution of the transport equation) is not easy to make.

Re: Using Input Macroscopic Cross Section Libraries

Posted: Tue Feb 23, 2021 7:27 pm
by PRoux
Okay, that is what I thought, but it doesn't hurt to check!
Thanks Ana and Jaakko.