Hi Paul. I am a little bit confused with your second answer.
My source distribution does contain two separate sources (neutron and photon sources). Each source has the same strength (1, strength value by default).
Defining the sources:
neutron_source = openmc.Source()
neutron_source.space = openmc.stats.Point(xyz=(0.0,0.0,0.0))
neutron_source.energy = openmc.stats.Tabular(NE,NP,interpolation=‘histogram’)
photon_source = openmc.Source()
photon_source.space = openmc.stats.Point(xyz=(0.0,0.0,0.0))
photon_source.energy = openmc.stats.Tabular(GE,GP,interpolation=‘histogram’)
photon_source.particle = ‘photon’
settings.source = [neutron_source,photon_source]
I am tallying the neutron and photon fluxes using particle and mesh filters. Then, loading the results as follows (ne is the number of mesh elements that is the same in x and y directions):
sp = openmc.StatePoint(‘statepoint.300.h5’)
flux_neutrons = sp.get_tally(name=‘Neutrons’).get_pandas_dataframe()
flux_neutrons = flux_neutrons[‘mean’].values.reshape((ne,ne))
flux_photons = sp.get_tally(name=‘Photons’).get_pandas_dataframe()
flux_photons = flux_photons[‘mean’].values.reshape((ne,ne))
If I understood correctly, these results are normalized “per source particle”. Then, multiplying the neutron and photon flux values by 2, I will get the results normalized “per source neutron” and “per source photon”, respectively.
neutrons_flux = 2*flux_neutrons
photon_flux = 2*flux_photons
After that, I can transform the flux units to conventional units using the equation described in a previous post considering the neutron and photon source intensities with the respective flux values.
Is this the correct procedure?
Thanks,
Maria