I followed the steps in the post here: OpenMC cross_section.xml problem but I still got the same error, I’m not sure what I did wrong, here’s what I typed in the terminal, I still get the error no cross sections. xml file was specified, I downloaded ENDF/B-VII.1 and my openmc version is 0.13.1, I’m using ubuntu:
I tried changing the location of the downloaded folder im openmc-env and it still gives me the error that the file in that location doesn’t exist:
I also tried opening it in the terminal:
openmc.plot_geometry(output=False)
I also get these messages and I’m not sure I quite understand it:
@Pranto Could you help, please?
I tried the fix in here and it seems to work, I finally got a different error: GitHub - openmc-data-storage/openmc_data_downloader: A Python package for downloading h5 cross section files for use in OpenMC.
Hi @Dalia,
Can you specify what fix you used from the data downloader?
Tagging @shimwell here, the author of that package.
-Patrick
Just to mention that issue got solved over in another thread with this comment Could not find nuclide U235 - #8 by Shimwell
I used the lines in this GitHub source: GitHub - openmc-data-storage/openmc_data_downloader: A Python package for downloading h5 cross section files for use in OpenMC. made by @Shimwell and I also needed to include missing nuclides: openmc_data_downloader -l TENDL-2019 -e U Li Na Si Fe O H B Zr
With the help of @Shimwell