Error in OpenMC Transport-Independent depletion v 0.14.0

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1

When running a transport independent depletion case in OpenMC I am getting the following error:

[openmc.deplete] t=0.0 s, dt=697641.8061681102 s, source=10000000.0
No energy reported from OpenMC tallies. Do your HDF5 files have heating data?

Using the OpenMC official ENDF 7.1 data library and generating the flux and cross sections using the get_micros_and_flux() function for a single energy group

2

There are a few other topics on this in the forum which point to not using the official libraries (as you allude to), but I found that I receive this ā€œNo energy reportedā€ error when settings.run_mode was not set to ā€˜eigenvalueā€™ (in my case due to prior volume calculations).

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