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