openmc.lib.Material

class openmc.lib.Material(uid=None, new=True, index=None)

Material stored internally.

This class exposes a material that is stored internally in the OpenMC library. To obtain a view of a material with a given ID, use the openmc.lib.materials mapping.

Parameters:

• uid (int or None) – Unique ID of the material
• new (bool) – When index is None, this argument controls whether a new object is created or a view to an existing object is returned.
• index (int or None) – Index in the materials array.

Variables:

• id (int) – ID of the material
• nuclides (list of str) – List of nuclides in the material
• densities (numpy.ndarray) – Array of densities in atom/b-cm
• name (str) – Name of the material
• temperature (float) – Temperature of the material in [K]
• volume (float) – Volume of the material in [cm^3]

add_nuclide(name, density)

Add a nuclide to a material.

Parameters:

• name (str) – Name of nuclide, e.g. ‘U235’
• density (float) – Density in atom/b-cm

set_densities(nuclides, densities)

Set the densities of a list of nuclides in a material

Parameters:

• nuclides (iterable of str) – Nuclide names
• densities (iterable of float) – Corresponding densities in atom/b-cm

set_density(density, units='atom/b-cm')

Set density of a material.

Parameters:

• density (float) – Density
• units ({'atom/b-cm', 'g/cm3'}) – Units for density