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OpenMC 0.6.1
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@paulromano paulromano released this 13 Oct 23:44
v0.6.1
5184ca6

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

  • 03e8903 Check for energy-dependent multiplicities in ACE files
  • 4439de5 Fix distance-to-surface calculation for general plane surface
  • 5808ed4 Account for differences in URR band probabilities at different energies
  • 2e60c0e Allow zero atom/weight percents in materials
  • 3e0870a Don't use PWD environment variable when setting path to input files
  • dc47763 Handle probability table resampling correctly
  • 01178bf Fix metastables nuclides in NNDC cross_sections.xml file
  • 62ec431 Don't read tallies.xml when OpenMC is run in plotting mode
  • 2a95ef7 Prevent segmentation fault on "current" score without mesh filter
  • 93e4823 Check for negative values in probability tables
  • 9d32299 Ensure installation of Python modules goes into correct directory

Contributors

This release contains new contributions from the following people:

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