Open mc flux tally relevant problem for a pin cell analysis.

I’m trying to find the neutron flux profle along the z axis (vertically).This model is pin cell model .Geometry is Ok.However, flux is not found yet .showing this error:

with openmc.StatePoint(‘statepoint.210.h5’) as sp:df = sp.tallies[flux_tally.id].get_pandas_dataframe()

Please comment if you could give any solution.
thanks in advance.

For getting flux value along z axis, u should define MeshFilter along z axis for scoring flux.

Best regards
Pranto