Cross-section generation questions

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Cross-section generation questions

Post by j0937065063 » Fri Mar 06, 2020 9:16 am

Hi Jaakko,

The scattering matrix generated by the detector is an "averaged" homogenized cross-section for the whole model, is that correct? e.g. INF_SCATT0, INF_SCATTP0 ... etc.

Is there a way to generate material dependent macroscopic cross-section, including total, absorption, nu*fission, and P0, P1, P2, P3 .... scattering matrices?

I am trying to generate some multi-group cross-section for transport code calculations.



Ville Valtavirta
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Re: Cross-section generation questions

Post by Ville Valtavirta » Mon Mar 09, 2020 10:55 am

Hi Vince,

Serpent does the group constant generation on universe basis, which means that you can get material-wise homogenized group constants by specifying different materials as different universes. The most simple approach would probably be to create an inf surface and create separate infinite cells/universes for different materials. Then you can replace the materials in cell, pin etc. definitions by filling in the corresponding universe instead.

Finally, set group constant generation on for all relevant universes using the set gcu card.


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