material problem

User Support
1

hi all

i think i have a probleme that influences the keff ,

here when i give this input python:

UO2= openmc.Material(material_id=3, name=‘UO2 fuel at 2% wt enrichment’)
UO2.set_density(‘g/cc’, 10.24)
UO2.add_element(‘U’ , 0.0208924, ‘wo’)
UO2.add_element(‘U’ , 0.8606417, ‘wo’)
UO2.add_element(‘O’, 0.1184610, ‘wo’)

i get this output XML

Any help ?. Thank you

2

UO2.set_density('g/cc', 10.24)
UO2.add_nuclide('U235' , 0.0208924, 'wo')
UO2.add_nuclide('U238' , 0.8606417, 'wo')
UO2.add_element('O', 0.1184610, 'wo')

I think this will solve your problem.