openmc-dev/openmc: OpenMC 0.12.2

This release of OpenMC is primarily a hotfix release with numerous important bug fixes. Several tally-related enhancements have also been added. New Features Three tally-related enhancements were added to the code in this release: A new CollisionFilter class that allows tallies to be filtered by the number of collisions a particle has undergone. A translation attribute has been added to MeshFilter that allows a mesh to be translated from its original position before location checks are performed. The UnstructuredMesh class now supports libMesh unstructured meshes to enable better ingration with MOOSE-based applications. Bug Fixes Reset particle coordinates during find cell operation Cover quadric edge case Prevent divide-by-zero in bins_crossed methods for meshes Fix for translational periodic boundary conditions Fix angle sampling in CorrelatedAngleEnergy Fix typo in fmt string for a lattice error Nu-fission tally and stochastic volume bug fixes Make sure failed neighbor list triggers exhaustic search Change element to element.title to catch lowercase entries Disallow non-current scores with a surface filter Depletion operator obeys Materials.cross_sections Fix for surface_bins_crossed override Contributors This release contains new contributions from the following people: @HunterBelanger @isaac-gs @drewejohnson @gridley @paulromano @pshriwise @Shimwell @ameliaj