Open shimwell opened 1 year ago
error caused when expanding a element without a cross section file set
import openmc import openmc_data_downloader openmc.config['cross_sections']='' mat1 = openmc.Material() mat1.add_element('Li', 1) mat1.set_density('g/cm3',1) materials=openmc.Materials([mat1]) materials.download_cross_section_data( libraries=["FENDL-3.1d"], set_OPENMC_CROSS_SECTIONS=True, particles=["neutron"], ) surf1 = openmc.Sphere(r=10, boundary_type='vacuum') region1 = -surf1 cell1=openmc.Cell(region=region1,fill=mat1) geometry=openmc.Geometry([cell1]) point = openmc.stats.Point((0, 0, 0)) energy = openmc.stats.Discrete([14.1e6], [1.0]) source = openmc.Source(space=point, energy=energy) settings = openmc.Settings() settings.source = source settings.run_mode = 'fixed source' settings.particles = 10000 settings.batches = 10 model = openmc.Model(geometry, materials, settings) model.run()
ile ~/venv/openmc_env/lib/python3.8/site-packages/openmc/material.py:744, in Material.add_element(self, element, percent, percent_type, enrichment, enrichment_target, enrichment_type) 742 # Add naturally-occuring isotopes 743 element = openmc.Element(element) --> 744 for nuclide in element.expand(percent, 745 percent_type, 746 enrichment, 747 enrichment_target, 748 enrichment_type): 749 self.add_nuclide(*nuclide) File ~/venv/openmc_env/lib/python3.8/site-packages/openmc/element.py:138, in Element.expand(self, percent, percent_type, enrichment, enrichment_target, enrichment_type, cross_sections) 136 if cross_sections is not None: 137 library_nuclides = set() --> 138 tree = ET.parse(cross_sections) 139 root = tree.getroot() 140 for child in root.findall('library'): File /usr/lib/python3.8/xml/etree/ElementTree.py:1202, in parse(source, parser) 1193 """Parse XML document into element tree.
perhaps natural element compositions could be used if a cross section xml file is not found
error caused when expanding a element without a cross section file set