New Pincell Depletion Error

Hello,

I tried running the pincell depletion example from another computer and rather than encountering the previous problem, I am now met by this in my command prompt

(openmc-env) amasri@amasri:~/depdep$ python run_depletion.py
Traceback (most recent call last):
File “/home/amasri/depdep/run_depletion.py”, line 15, in
op = openmc.deplete.Operator(model, chain_file)
File “/home/amasri/miniconda3/envs/openmc-env/lib/python3.10/site-packages/openmc/deplete/operator.py”, line 294, in init
self.nuclides_with_data = self._get_nuclides_with_data(cross_sections)
File “/home/amasri/miniconda3/envs/openmc-env/lib/python3.10/site-packages/openmc/deplete/operator.py”, line 787, in _get_nuclides_with_data
data_lib = DataLibrary.from_xml(cross_sections)
File “/home/amasri/miniconda3/envs/openmc-env/lib/python3.10/site-packages/openmc/data/library.py”, line 149, in from_xml
tree = ET.parse(path)
File “/home/amasri/miniconda3/envs/openmc-env/lib/python3.10/xml/etree/ElementTree.py”, line 1229, in parse
tree.parse(source, parser)
File “/home/amasri/miniconda3/envs/openmc-env/lib/python3.10/xml/etree/ElementTree.py”, line 580, in parse
self._root = parser._parse_whole(source)
xml.etree.ElementTree.ParseError: junk after document element: line 971, column 0

Does anyone know how I can remedy this, or the problem encountered in this thread

Thank you

The error you’re seeing is happening when OpenMC is trying to inspect what cross section data is available:

To do this, it looks at the OPENMC_CROSS_SECTIONS environment variable. Have you set up this environment variable? If not, please see the relevant user’s guide section.