`get_photon_contact_dose_rate()` crashes after depletion because of nuclides above Z=100

[eitan-maker1997]

Bug Description

Hello. I found a problem with Material.get_photon_contact_dose_rate() after depletion.

Steps to Reproduce

This small example depletes UO2 for one day and then calculates the contact dose rate:

import openmc
import openmc.deplete


fuel = openmc.Material()
fuel.set_density("g/cm3", 10.5)
fuel.add_nuclide("U235", 0.05)
fuel.add_nuclide("U238", 0.95)
fuel.add_nuclide("O16", 2.0)
fuel.volume = 1000.0
fuel.depletable = True

flux = [1.0]
micros = openmc.deplete.MicroXS.from_multigroup_flux(
    [0.0, 20.0e6], flux, nuclides=["U235", "U238"], reactions=["fission"]
)
operator = openmc.deplete.IndependentOperator([fuel], [flux], [micros])
integrator = openmc.deplete.PredictorIntegrator(
    operator, [1.0], power=1.0e6, timestep_units="d"
)
integrator.integrate(path="depletion_results.h5")

depleted_fuel = openmc.deplete.Results("depletion_results.h5")[-1].get_material(
    fuel.id
)
print(depleted_fuel.get_photon_contact_dose_rate())

The last line fails with ValueError: No mass attenuation data available for Z=104.

After depletion, the material contains very small amounts of Rf265 (Z=104), Sg269 (Z=106), and Hs273 (Z=108). For example, Rf265 has density around 2.6e-36 atom/b-cm in this case. get_photon_contact_dose_rate() tries to get mass attenuation data for every nuclide before it checks if the nuclide has a decay-photon source. The bundled attenuation data stops at Z=100, so the calculation crashes because of these trace nuclides.

I think the CDR calculation should still work for the rest of the material in this case, for example by skipping nuclides with no decay-photon source before requesting attenuation data, or by handling missing attenuation data in another way.

Tested with OpenMC 0.16.1.dev8+g7ecd3a961.