openmc interop

Getting an inventory out of OpenMC without depending on it.

openmc_interop

Getting an inventory out of OpenMC without depending on it.

OpenMC is imported only inside these functions and only when they are called, so installing this package pulls in nothing, and everything except these two functions works with no OpenMC present.

Functions:

• from_openmc_material –

  Convert an openmc.Material into a Material.

• from_depletion_results –

  Build a cooling time series from an OpenMC depletion results file.

from_openmc_material

from_openmc_material(openmc_material, *, decay_data=None) -> Material

Convert an openmc.Material into a Material.

Reads the atom densities in atoms per barn-cm, which fixes the mass density too, so the result supports both the Bq/g and the Ci/m3 limit sets.

Parameters:

• openmc_material

  –

  An openmc.Material. Its nuclides must be expanded, which get_nuclide_atom_densities does.

• decay_data

  –

  Half-life and mass tables to use instead of the defaults.

Returns:

• Material –

  The equivalent Material, carrying the OpenMC material's name

• Material –

  and volume where it has them.

from_depletion_results

from_depletion_results(results, material_id, *, decay_data=None) -> dict[float, Material]

Build a cooling time series from an OpenMC depletion results file.

The result is in the form time_to_clear expects, so a depletion can be taken straight through to a clearance date.

Parameters:

• results

  –

  An openmc.deplete.Results object.

• material_id

  –

  The depleted material's id, as a string or int.

• decay_data

  –

  Half-life and mass tables to use instead of the defaults.

Returns:

• dict[float, Material] –

  Time in seconds since the start of the results to the material at that

• dict[float, Material] –

  time.