Using Input Macroscopic Cross Section Libraries

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PRoux
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Using Input Macroscopic Cross Section Libraries

Post by PRoux » Tue Feb 23, 2021 6:10 pm

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 !

Ana Jambrina
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Re: Using Input Macroscopic Cross Section Libraries

Post by Ana Jambrina » Tue Feb 23, 2021 7:06 pm

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).
- Ana

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Jaakko Leppänen
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Re: Using Input Macroscopic Cross Section Libraries

Post by Jaakko Leppänen » Tue Feb 23, 2021 7:06 pm

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.
- Jaakko

PRoux
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Re: Using Input Macroscopic Cross Section Libraries

Post by PRoux » Tue Feb 23, 2021 7:27 pm

Okay, that is what I thought, but it doesn't hurt to check!
Thanks Ana and Jaakko.

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