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Traceback (most recent call last):
File "/theory/pyoung/.local/bin/mcnp_to_openmc", line 8, in
sys.exit(mcnp_to_openmc())
^^^^^^^^^^^^^^^^
File "/theory/pyoung/.local/lib/python3.11/site-packages/openmc_mcnp_adapter/openmc_conversion.py", line 719, in mcnp_to_openmc
model = mcnp_to_model(args.mcnp_filename)
^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^
File "/theory/pyoung/.local/lib/python3.11/site-packages/openmc_mcnp_adapter/openmc_conversion.py", line 689, in mcnp_to_model
openmc_universes = get_openmc_universes(cells, openmc_surfaces,
^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^
File "/theory/pyoung/.local/lib/python3.11/site-packages/openmc_mcnp_adapter/openmc_conversion.py", line 431, in get_openmc_universes
universes[uid].add_cell(cell)
^^^^^^^^^^^^^^^^^^^^^^^
AttributeError: 'RectLattice' object has no attribute 'add_cell'
Traceback (most recent call last):
File "/theory/pyoung/.local/bin/mcnp_to_openmc", line 8, in
sys.exit(mcnp_to_openmc())
^^^^^^^^^^^^^^^^
File "/theory/pyoung/.local/lib/python3.11/site-packages/openmc_mcnp_adapter/openmc_conversion.py", line 719, in mcnp_to_openmc
model = mcnp_to_model(args.mcnp_filename)
^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^
File "/theory/pyoung/.local/lib/python3.11/site-packages/openmc_mcnp_adapter/openmc_conversion.py", line 689, in mcnp_to_model
openmc_universes = get_openmc_universes(cells, openmc_surfaces,
^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^
File "/theory/pyoung/.local/lib/python3.11/site-packages/openmc_mcnp_adapter/openmc_conversion.py", line 553, in get_openmc_universes
univ_ids = np.asarray(univ_ids, dtype=int)
^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^
ValueError: invalid literal for int() with base 10: '(2'
The first can be solved by commenting out cell 701. But the converter should be able to accept it as it.
The second, trcl=(2 3 0) has to be removed, and then the converter works. But the translation is lost.
The text was updated successfully, but these errors were encountered:
Could you please update your example to be a full minimum working example, i.e., it could be opened as a valid input by MCNP. You can set your surfaces to be nonsensical to remove any sensitive information.
It's unclear to me if this officially supports matrix fills like you have used here or not.
The following works in MCNP but is not accepted by the converter.
Versions:
openmc_mcnp_adapter 0.1.0 (latest)
Python3.11
Two problems occur:
The text was updated successfully, but these errors were encountered: