Problem with openmc.MeshSurfaceFilter (OpenMC hangs)

User Support
1

Hello OpenMC community,

I ran recently in a problem when using the openmc.MeshSurfaceFilter

At a certain point the simulations just hangs at a certain batch (and most likely a particle)
and just won’t continue.

I put below a version of our model that is reduced to the bare minimum to demonstrate the issue.

A simple mono-energetic Source of quadratic-plane shape and a little farther away a rectangular
RegularMesh. On this mesh the current is tallied with the openmc.MeshSurfaceFilter.
All with fill = None, so no materials involved.

With the particular setting of seed to settings.seed = 21 the simulation hengs forever in the third simulated batch.
Changing the seed value just shifts the time, when the problem occurs

I am using the last versi

on of OpenMC ( 0.14.1), but the error occurred at the previous release, too

I tried to get some debug info by increasing verbosity and even by using a debugBuild of OpenMC, but got no leads from that.

Any help would be appreciated. I can of course run more tests on demand and advice.

Best
Richard

Simple_model_meshsurface_debug.ipynb (111.6 KB)

2

Hi,

Since there was no response -
would it be better to open an issue so someone can hava a look at the problem?
Or look for workarounds as to not use MeshSurfaceFilter for e.g.?

I suspect a pure geometric reason since there is no material involved in the test case.

Thanks,

Richard

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                 | The OpenMC Monte Carlo Code
       Copyright | 2011-2023 MIT, UChicago Argonne LLC, and contributors
         License | https://docs.openmc.org/en/latest/license.html
         Version | 0.14.1-dev
        Git SHA1 | ec8850deac2046668ab087f1f5f14a9df4614008
       Date/Time | 2024-01-15 17:11:07
  OpenMP Threads | 48

 Reading model XML file './model.xml' ...
 WARNING: Other XML file input(s) are present. These files may be ignored in
          favor of the ./model.xml file.
 Reading cross sections XML file...
 Minimum neutron data temperature: 1.7976931348623157e+308 K
 Maximum neutron data temperature: 0 K
 Preparing distributed cell instances...
 Writing summary.h5 file...

 ===============>     FIXED SOURCE TRANSPORT SIMULATION     <===============

 Simulating batch 1
 Simulating batch 2
 Simulating batch 3

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