CalledProcessError: Command 'openmc' died with <Signals.SIGSEGV: 11>

User Support
1

Hi All,

I’m new to using OpenMC. I’m creating my first model and have received a segmentation fault upon running:

CalledProcessError: Command 'openmc' died with <Signals.SIGSEGV: 11>.

In Open MC I get this read out:
Reading settings XML file…
Reading cross sections XML file…
Reading materials XML file…
Reading geometry XML file…
Reading H1 from /home/alletro/openmc/endfb80_hdf5/H1.h5
Reading H2 from /home/alletro/openmc/endfb80_hdf5/H2.h5
Reading O16 from /home/alletro/openmc/endfb80_hdf5/O16.h5
Reading O17 from /home/alletro/openmc/endfb80_hdf5/O17.h5
Reading O18 from /home/alletro/openmc/endfb80_hdf5/O18.h5
Reading Al27 from /home/alletro/openmc/endfb80_hdf5/Al27.h5
Reading N14 from /home/alletro/openmc/endfb80_hdf5/N14.h5
Reading N15 from /home/alletro/openmc/endfb80_hdf5/N15.h5
Reading Ar40 from /home/alletro/openmc/endfb80_hdf5/Ar40.h5
Reading Ar36 from /home/alletro/openmc/endfb80_hdf5/Ar36.h5
WARNING: Negative value(s) found on probability table for nuclide Ar36 at 294K
Reading Ar38 from /home/alletro/openmc/endfb80_hdf5/Ar38.h5
Reading C13 from /home/alletro/openmc/endfb80_hdf5/C13.h5
Reading C12 from /home/alletro/openmc/endfb80_hdf5/C12.h5
Reading Mo98 from /home/alletro/openmc/endfb80_hdf5/Mo98.h5
Minimum neutron data temperature: 294.000000 K
Maximum neutron data temperature: 294.000000 K
Reading tallies XML file…
Preparing distributed cell instances…
Writing summary.h5 file…
Maximum neutron transport energy: 20000000.000000 eV for H1
Initializing source particles…

 ====================>     K EIGENVALUE SIMULATION     <====================

  Bat./Gen.      k            Average k
  =========   ========   ====================
 ERROR: No fission sites banked on MPI rank 0

I am running openMC on python 3.8.5, installed through conda. My operating system is Ubuntu 20.04. I’m running gon a Dell Latitude 3301 with an intel i5 and 8GB of ram. My initial thought was a memory issue. I’ve closed all other programs and monitored system usage and not seen a spike in memory usage.

I found a similar question on GitHub:

Their issue seemed to related to the conversion from MCNP, which I am not doing. I have checked for a boundary issue and couldn’t spot anything. I could not find a log file produced with any more information. I have checked my outer sphere has a boundary_type=‘vacuum’.

Another issue

I have altered the batches, particles and inactive but no combination has resolved the issue. I imagine I have made a clear mistake in my code but cannot debug it. Any assistance would be greatly appreciated. I have attached my code below:

open with the password: OPENMC

2

@alletro OpenMC runs a k-eigenvalue calculation by default. It looks like you are trying to run a fixed source problem here, so you’ll need one extra line:

sett.run_mode = 'fixed source'