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ReStructuredText
94 lines
3.9 KiB
ReStructuredText
===================
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What's New in 0.8.0
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===================
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This release of OpenMC includes a few new major features including the
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capability to perform neutron transport with multi-group cross section data as
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well as experimental support for the windowed multipole method being developed
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at MIT. Source sampling options have also been expanded significantly, with the
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option to supply arbitrary tabular and discrete distributions for energy, angle,
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and spatial coordinates.
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The Python API has been significantly restructured in this release compared to
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version 0.7.1. Any scripts written based on the version 0.7.1 API will likely
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need to be rewritten. Some of the most visible changes include the following:
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- ``SettingsFile`` is now ``Settings``, ``MaterialsFile`` is now ``Materials``,
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and ``TalliesFile`` is now ``Tallies``.
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- The ``GeometryFile`` class no longer exists and is replaced by the
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``Geometry`` class which now has an ``export_to_xml()`` method.
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- Source distributions are defined using the ``Source`` class and assigned to
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the ``Settings.source`` property.
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- The ``Executor`` class no longer exists and is replaced by ``openmc.run()``
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and ``openmc.plot_geometry()`` functions.
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The Python API documentation has also been significantly expanded.
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-------------------
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System Requirements
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-------------------
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There are no special requirements for running the OpenMC code. As of this
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release, OpenMC has been tested on a variety of Linux distributions and Mac
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OS X. Numerous users have reported working builds on Microsoft Windows, but your
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mileage may vary. Memory requirements will vary depending on the size of the
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problem at hand (mostly on the number of nuclides and tallies in the problem).
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------------
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New Features
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------------
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- Multi-group mode
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- Vast improvements to the Python API
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- Experimental windowed multipole capability
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- Periodic boundary conditions
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- Expanded source sampling options
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- Distributed materials
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- Subcritical multiplication support
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- Improved method for reproducible URR table sampling
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- Refactor of continuous-energy reaction data
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- Improved documentation and new Jupyter notebooks
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---------
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Bug Fixes
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---------
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- 70daa7_: Make sure MT=3 cross section is not used
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- 40b05f_: Ensure source bank is resampled for fixed source runs
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- 9586ed_: Fix two hexagonal lattice bugs
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- a855e8_: Make sure graphite models don't error out on max events
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- 7294a1_: Fix incorrect check on cmfd.xml
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- 12f246_: Ensure number of realizations is written to statepoint
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- 0227f4_: Fix bug when sampling multiple energy distributions
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- 51deaa_: Prevent segfault when user specifies '18' on tally scores
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- fed74b_: Prevent duplicate tally scores
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- 8467ae_: Better threshold for allowable lost particles
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- 493c6f_: Fix type of return argument for h5pget_driver_f
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.. _70daa7: https://github.com/openmc-dev/openmc/commit/70daa7
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.. _40b05f: https://github.com/openmc-dev/openmc/commit/40b05f
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.. _9586ed: https://github.com/openmc-dev/openmc/commit/9586ed
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.. _a855e8: https://github.com/openmc-dev/openmc/commit/a855e8
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.. _7294a1: https://github.com/openmc-dev/openmc/commit/7294a1
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.. _12f246: https://github.com/openmc-dev/openmc/commit/12f246
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.. _0227f4: https://github.com/openmc-dev/openmc/commit/0227f4
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.. _51deaa: https://github.com/openmc-dev/openmc/commit/51deaa
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.. _fed74b: https://github.com/openmc-dev/openmc/commit/fed74b
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.. _8467ae: https://github.com/openmc-dev/openmc/commit/8467ae
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.. _493c6f: https://github.com/openmc-dev/openmc/commit/493c6f
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------------
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Contributors
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------------
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This release contains new contributions from the following people:
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- `Will Boyd <wbinventor@gmail.com>`_
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- `Derek Gaston <friedmud@gmail.com>`_
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- `Sterling Harper <sterlingmharper@gmail.com>`_
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- `Colin Josey <cjosey@mit.edu>`_
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- `Jingang Liang <liangjg2008@gmail.com>`_
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- `Adam Nelson <nelsonag@umich.edu>`_
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- `Paul Romano <paul.k.romano@gmail.com>`_
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- `Kelly Rowland <kellylynnerowland@gmail.com>`_
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- `Sam Shaner <samuelshaner@gmail.com>`_
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