OpenMC version 0.6.1

Hi all,

The OpenMC development team is proud to announce the release of version 0.6.1. This release includes various new features and bug fixes added over the past three months.

New features in version 0.6.1 include:

  • 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 include:
  • 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
    I’d like to thank Bryan Herman, Adam Nelson, Jon Walsh, Sterling Harper, and Will Boyd for their contributions to this release. The source code can be downloaded at or the master branch on the GitHub Repository.

Best regards,