Seg fault in 0.14.1

User Support
1

Hey guys, I’m getting a seg fault (below) on a recent build:

 Initializing source particles...

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

[luke-hpz840workstation:61946] *** Process received signal ***
[luke-hpz840workstation:61946] Signal: Segmentation fault (11)
[luke-hpz840workstation:61946] Signal code: Address not mapped (1)
[luke-hpz840workstation:61946] Failing at address: (nil)
[luke-hpz840workstation:61946] [ 0] /usr/lib/libc.so.6(+0x3e710)[0x7f21a845c710]
[luke-hpz840workstation:61946] *** End of error message ***
Traceback (most recent call last):
  File "/home/luke/git/are/scripts/ARE_fuel_reactivity_coefficient.py", line 23, in <module>
    sp_filepath = model.run(output = True)
                  ^^^^^^^^^^^^^^^^^^^^^^^^
  File "/usr/lib/python3.11/site-packages/openmc/model/model.py", line 711, in run
    openmc.run(particles, threads, geometry_debug, restart_file,
  File "/usr/lib/python3.11/site-packages/openmc/executor.py", line 314, in run
    _run(args, output, cwd)
  File "/usr/lib/python3.11/site-packages/openmc/executor.py", line 125, in _run
    raise RuntimeError(error_msg)
RuntimeError: OpenMC aborted unexpectedly.

output when run with executable

[luke-hpz840workstation:62768] Signal: Segmentation fault (11)
[luke-hpz840workstation:62768] Signal code: Address not mapped (1)
[luke-hpz840workstation:62768] Failing at address: (nil)
[luke-hpz840workstation:62768] [ 0] /usr/lib/libc.so.6(+0x3e710)[0x7f115be5c710]
[luke-hpz840workstation:62768] *** End of error message ***
zsh: segmentation fault (core dumped)  openmc

output of openmc --version

OpenMC version 0.14.1
Git SHA1: 3901709141f6e1e85707fa1ce901199df081cc29
Copyright (c) 2011-2023 MIT, UChicago Argonne LLC, and contributors
MIT/X license at <https://docs.openmc.org/en/latest/license.html>
Build type:            RelWithDebInfo
Compiler ID:           GNU 13.2.1
MPI enabled:           yes
Parallel HDF5 enabled: yes
PNG support:           yes
DAGMC support:         yes
libMesh support:       no
MCPL support:          no
NCrystal support:      no
Coverage testing:      no
Profiling flags:       no

and the model (if relevant):

################################################################################
#test script

#from https://docs.openmc.org/en/stable/examples/post-processing.html
################################################################################
import openmc

# materials
# 1.6 enriched fuel
fuel = openmc.Material(name='fuel')
fuel.set_density('g/cm3', 10.31341)
fuel.add_nuclide('U235', 3.7503e-4)
fuel.add_nuclide('U238', 2.2625e-2)
fuel.add_nuclide('O16', 4.6007e-2)

# cladding
cladding = openmc.Material(name='cladding')
cladding.set_density('g/cm3', 6.55)
cladding.add_nuclide('Zr90', 7.2758e-3)

# borated water
water = openmc.Material(name='water')
water.set_density('g/cm3', 0.740582)
water.add_nuclide('H1', 4.9457e-2)
water.add_nuclide('O16', 2.4732e-2)
water.add_nuclide('B10', 8.0042e-6)

# Instantiate a Materials collection
materials = openmc.Materials([fuel, water, cladding])

# Export to "materials.xml"
materials.export_to_xml()

#Geometry
h5m_filepath = 'dagmc.h5m'
graveyard=openmc.Sphere(r=10000,boundary_type='vacuum')
cad_univ = openmc.DAGMCUniverse(filename=h5m_filepath,auto_geom_ids=True,universe_id=996 )
cad_cell = openmc.Cell(cell_id=997 , region= -graveyard, fill= cad_univ)
root = openmc.Universe(universe_id=998)
root.add_cells([cad_cell])
geometry = openmc.Geometry(root)
geometry.export_to_xml()

# OpenMC simulation parameters
settings = openmc.Settings()
settings.batches = 100
settings.inactive = 10
settings.particles = 5000

# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-10, -10, -10, 10, 10, 10]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings.source = openmc.Source(space=uniform_dist)

# Export to "settings.xml"
settings.export_to_xml()

# Run OpenMC!
openmc.run()

I will continue looking into this, but ideas are appreciated. Thanks!

Luke