I have installed the new version of openmc (0.7.0) compiled from source using FC=mpif90.openmpi for the compilation, as well as installing ipython, numpy, scipy, matplotlib, and vtk. My OS is linux mint 17.1 cinammon (Rebecca), 64 bit architecture.
The executable openmc-plot-mesh-tally gives me the following error when executed on an arbitrary statepoint binary:
AttributeError: ‘Tally’ object has no attribute ‘get_value’
I am reluctant to over-think this. Is there a problem with the script, or do I have other issues?
Your assistance is greatly appreciated!
Shawn Wachter
Kansas City, MO
816 337 7003
Shawn,
I think this is unfortunately a bug that crept in during some of the most recent changes to the Python API in OpenMC. I just submitted a bug fix for this to GitHub (here) for code review.
In the meantime, if you change “get_value” to “get_vaues” in the Python script I believe it will work for you.
Best,
Will
Shawn- here’s a version of openmc-plot-mesh-tally I just hacked up that should work. Will and I are working on getting the fix into the develop branch and will let you know when that happens. Thanks for helping to find a bug!
Best,
Paul
openmc-plot-mesh-tally (11 KB)
Shawn,
Paul and I merged in a patch to correct a few bugs in the openmc-plot-mesh-tally script which you can see on GitHub here. This is not part of the official v0.7 release, but you can easily access it by switching to the “develop” Git branch (the default branch when you clone the repository from GitHub). Then simply call “git pull” to merge in our latest changes.
Sorry for the inconvenience, thanks for pointing out this issue!
Best,
Will
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Am still unable to get the openmc-plot-mesh-tally script to work properly. It will now produce a graph for the test_filter_mesh_2d test case, but it hangs up on the test_filter_energy test case, which I have modified by adding a rectangular mesh.
A screenshot is included, as is the modified tallies.xml file.
The affected files seem to be openmc-plot-mesh-tally , tallies.py , and filter.py . I wonder if the problem could be that there is a variable name filter_bin in one script, and a variable named filter_bins in another ?
I am trying to produce simultaneous graphs of both the thermal and fast absorption fluxes - and fluxes specific to certain isotopes, such as Np-237. My installation of the previous version, 0.6.2, had this capability. These visualizations are very helpful, as I am modeling an MSR core that irradiates various blanket materials.
Respectfully,
Shawn W.
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tallies.xml (420 Bytes)
Shawn,
Can you try the version of openmc-plot-mesh-tally that I’ve attached? I’ve tested it out on test_filter_energy with your tallies.xml file and it works for me. Once you give me the green light, I will go ahead and submit a pull request so we can get this in the main codebase.
Thanks again!
Paul
openmc-plot-mesh-tally (11.4 KB)
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The new script works on my setup.
Thanks,
Shawn W.
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