OpenMC 0.6.1

New Features

• Coarse mesh finite difference (CMFD) acceleration no longer requires PETSc
• Statepoint file numbering is now zero-padded
• Python scripts now compatible with Python 2 or 3
• Ability to run particle restarts in fixed source calculations
• Capability to filter box source by fissionable materials
• Nuclide/element names are now case insensitive in input files
• Improved treatment of resonance scattering for heavy nuclides

Bug Fixes

• Check for energy-dependent multiplicities in ACE files
• Fix distance-to-surface calculation for general plane surface
• Account for differences in URR band probabilities at different energies
• Allow zero atom/weight percents in materials
• Don't use PWD environment variable when setting path to input files
• Handle probability table resampling correctly
• Fix metastables nuclides in NNDC cross_sections.xml file
• Don't read tallies.xml when OpenMC is run in plotting mode
• Prevent segmentation fault on "current" score without mesh filter
• Check for negative values in probability tables
• Ensure installation of Python modules goes into correct directory

Contributors

This release contains new contributions from the following people:

• @bhermanmit
• @nelsonag
• @paulromano
• @smharper
• @walshjon
• @wbinventor