What’s New in 0.12.2

Summary

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:

• Hunter Belanger

• Isaac Griswold-Steiner

• Andrew Johnson

• Gavin Ridley

• Paul Romano

• Patrick Shriwise

• Jonathan Shimwell