Allow control of OpenMC depletion tallies

[aprilnovak]

Reason

In order for the MOOSE webserver depletion control to function properly, we need to be able to edit the tallies OpenMC automatically sets up for depletion. This includes:

• Pass the "possible" depleted nuclides (nuclides which may be created from depletion of a material) up from the depletion Python side, into Cardinal's C++ side. These will be used to then properly add those nuclides as filters on the reaction rate tallies needed for depletion.
• Create new tallies
• Change tally filters

Design

Create a user object (or similar concept) to update the tallies and filters for OpenMC's depletion solver.

Impact

New feature to support depletion coupling.