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Thanks for making this package Paul
I've been trying to make use of endf.IncidentNeutron instead of openmc.IncidentNeutron for a plotting package I'm working on.
The first feature that appears to be different is the temperature attribute.
import openmc openmc_neutron = openmc.data.IncidentNeutron.from_ace('neutron_file/Li/006/lib/endf/Li006-n.ace') openmc_neutron.temperatures >>>['293K'] import endf endf_neutron = endf.IncidentNeutron.from_ace('neutron_file/Li/006/lib/endf/Li006-n.ace') endf_neutron.temperatures >>> AttributeError: module 'endf' has no attribute 'temperature'. Did you mean: 'temperature_str'?
Just wondering if adding temperature is on the roadmap
temperature
The text was updated successfully, but these errors were encountered:
looks like one can access the temperatures with this code
endf_neutron = endf.IncidentNeutron.from_ace('neutron_file/Li/006/lib/endf/Li006-n.ace') reactions=endf_neutron.reactions[1] temperatures=list(reactions.xs.keys())
So perhaps we could just add a getter to the IncidentNeutron class
Sorry, something went wrong.
If we do add tempertures then we could perhaps also sneak in IncidentNeutron.kTs which is in the openmc.IncidentNeutron and is the temperture in eV
IncidentNeutron.kTs
openmc.IncidentNeutron
Also openmc.IncidentNeutron.energy makes use of temperatures for the keys
openmc.IncidentNeutron.energy
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Thanks for making this package Paul
I've been trying to make use of endf.IncidentNeutron instead of openmc.IncidentNeutron for a plotting package I'm working on.
The first feature that appears to be different is the temperature attribute.
Just wondering if adding
temperature
is on the roadmapThe text was updated successfully, but these errors were encountered: