XS generation in Cylindrical Mesh

Hello everyone,

I am new to OpenMC and am still learning the features offered in this code. I’m wondering how to do cross-section generation in cylindrical geometry mesh. I would like to use the homogenized XS to run a diffusion code for HTR core analysis. I’m looking for some features similar to Serpent’s circular cluster array Input syntax manual - Serpent Wiki, or if there is some other approach I can use in OpenMC, please let me know.

Thank you.

Rizki Oktavian
PhD student, School of Nuclear Engineering
Purdue University

Hi, I have experience generating multigroup cross section in OpenMC. Hopefully I can help you!
OpenMC has a fantastic multigroup library feature that should make this easy for you.

Here is the most relevant OpenMC example: MGXS Part III: Libraries — OpenMC Documentation

All you need to do is define the mesh you want (in your case you will probably use the “unstructured mesh” to make it cylindrical) and then define a openmc.mgxs.Library object and assign your mesh as the domain.

Update: I think I was wrong in my first reply. It appears only RegularMesh is accepted as a domain, so I don’t think there is currently any support for other types of mesh. Sorry!

Hi,
Thanks for the response. I guess I’ll try to use other approaches.