Pincell depletion running issue

Hi,

Thanks for all the developer of OpenMC 0.11.0, this’s excellent work.

I’m trying to use new depletion function and merging it into whole reactor core simulation. However, I meet a problem when I work through ‘Pincell Depletion’ example. Jupyter kernel appears to have died when integrator.integrate() start reading the cross-section database. The chain file I’m using is PWR spectrum simplified chain which downloads from OpenMC data website, and the database is ENDF/B-BII.1.

Please contact me if you have any idea to fix this problem. Thank you very much.

Best wishes,
Yiming

1 Like

Hi Yiming- how much memory do you have on your machine? I wonder if perhaps you are running out of memory when nuclear data is being loaded.