I’m trying to understand how OpenMC handles density inputs when the density units are set before adding nuclides/elements. For example, we define the fuel for a fuel pin below:
# 1.6 enriched fuel
fuel = openmc.Material(name='1.6% Fuel')
fuel.set_density('g/cm3', 10.31341)
fuel.add_nuclide('U235', 3.7503e-4)
fuel.add_nuclide('U238', 2.2625e-2)
fuel.add_nuclide('O16', 4.6007e-2)
When I look at the documentation for openMC.material.add_nuclide, it says that the default unit for the second input of add_nuclide will be atom percent, so if we input the densities as above, does OpenMC sum those three floats, and their densities will be the relative percentages to the total for each nuclide input, and then that proportion of the total will be the nuclide density in g/cm3?
e.g. U235 density in g/cm3 would be calculated as 10.313 * 3.74e^-4/(sum of nuclide density inputs)?