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Incremented version number and added release notes
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Paul Romano
parent
bc2fab296b
commit
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6 changed files with 66 additions and 61 deletions
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@ -69,9 +69,9 @@ copyright = u'2011-2016, Massachusetts Institute of Technology'
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# built documents.
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#
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# The short X.Y version.
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version = "0.7"
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version = "0.8"
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# The full version, including alpha/beta/rc tags.
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release = "0.7.1"
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release = "0.8.0"
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# The language for content autogenerated by Sphinx. Refer to documentation
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# for a list of supported languages.
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@ -205,7 +205,7 @@ traveling in its current direction, it will not hit the surface. The complete
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derivation for different types of surfaces used in OpenMC will be presented in
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the following sections.
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Since :math:f(x,y,z)` in general is quadratic in :math:`x`, :math:`y`, and
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Since :math:`f(x,y,z)` in general is quadratic in :math:`x`, :math:`y`, and
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:math:`z`, this implies that :math:`f(x_0 + du_0, y + dv_0, z + dw_0)` is
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quadratic in :math:`d`. Thus we expect at most two real solutions to
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:eq:`dist-to-boundary-1`. If no solutions to :eq:`dist-to-boundary-1` exist or
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@ -1,78 +1,83 @@
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.. _releasenotes:
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==============================
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Release Notes for OpenMC 0.7.1
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Release Notes for OpenMC 0.8.0
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==============================
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This release of OpenMC provides some substantial improvements over version
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0.7.0. Non-simple cell regions can now be defined through the ``|`` (union) and
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``~`` (complement) operators. Similar changes in the Python API also allow
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complex cell regions to be defined. A true secondary particle bank now exists;
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this is crucial for photon transport (to be added in the next minor release). A
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rich API for multi-group cross section generation has been added via the
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``openmc.mgxs`` Python module.
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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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Various improvements to tallies have also been made. It is now possible to
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explicitly specify that a collision estimator be used in a tally. A new
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``delayedgroup`` filter and ``delayed-nu-fission`` score allow a user to obtain
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delayed fission neutron production rates filtered by delayed group. Finally, the
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new ``inverse-velocity`` score may be useful for calculating kinetics
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parameters.
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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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.. caution:: In previous versions, depending on how OpenMC was compiled binary
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output was either given in HDF5 or a flat binary format. With this
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version, all binary output is now HDF5 which means you **must**
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have HDF5 in order to install OpenMC. Please consult the user's
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guide for instructions on how to compile with HDF5.
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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, Mac OS X,
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and Microsoft Windows 7. Memory requirements will vary depending on the size of
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the problem at hand (mostly on the number of nuclides in the problem).
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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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- Support for complex cell regions (union and complement operators)
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- Generic quadric surface type
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- Improved handling of secondary particles
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- Binary output is now solely HDF5
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- ``openmc.mgxs`` Python module enabling multi-group cross section generation
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- Collision estimator for tallies
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- Delayed fission neutron production tallies with ability to filter by delayed
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group
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- Inverse velocity tally score
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- Performance improvements for binary search
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- Performance improvements for reaction rate tallies
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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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- 299322_: Bug with material filter when void material present
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- d74840_: Fix triggers on tallies with multiple filters
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- c29a81_: Correctly handle maximum transport energy
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- 3edc23_: Fixes in the nu-scatter score
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- 629e3b_: Assume unspecified surface coefficients are zero in Python API
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- 5dbe8b_: Fix energy filters for openmc-plot-mesh-tally
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- ff66f4_: Fixes in the openmc-plot-mesh-tally script
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- 441fd4_: Fix bug in kappa-fission score
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- 7e5974_: Allow fixed source simulations from Python API
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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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.. _299322: https://github.com/mit-crpg/openmc/commit/299322
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.. _d74840: https://github.com/mit-crpg/openmc/commit/d74840
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.. _c29a81: https://github.com/mit-crpg/openmc/commit/c29a81
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.. _3edc23: https://github.com/mit-crpg/openmc/commit/3edc23
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.. _629e3b: https://github.com/mit-crpg/openmc/commit/629e3b
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.. _5dbe8b: https://github.com/mit-crpg/openmc/commit/5dbe8b
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.. _ff66f4: https://github.com/mit-crpg/openmc/commit/ff66f4
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.. _441fd4: https://github.com/mit-crpg/openmc/commit/441fd4
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.. _7e5974: https://github.com/mit-crpg/openmc/commit/7e5974
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.. _70daa7: https://github.com/mit-crpg/openmc/commit/70daa7
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.. _40b05f: https://github.com/mit-crpg/openmc/commit/40b05f
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.. _9586ed: https://github.com/mit-crpg/openmc/commit/9586ed
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.. _a855e8: https://github.com/mit-crpg/openmc/commit/a855e8
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.. _7294a1: https://github.com/mit-crpg/openmc/commit/7294a1
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.. _12f246: https://github.com/mit-crpg/openmc/commit/12f246
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.. _0227f4: https://github.com/mit-crpg/openmc/commit/0227f4
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.. _51deaa: https://github.com/mit-crpg/openmc/commit/51deaa
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.. _fed74b: https://github.com/mit-crpg/openmc/commit/fed74b
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.. _8467ae: https://github.com/mit-crpg/openmc/commit/8467ae
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.. _493c6f: https://github.com/mit-crpg/openmc/commit/493c6f
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------------
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Contributors
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@ -81,11 +86,11 @@ Contributors
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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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- `Sterling Harper <sterlingmharper@mit.edu>`_
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- `Bryan Herman <hermab53@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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- `Jon Walsh <walshjon@mit.edu>`_
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@ -46,7 +46,7 @@ to locate ACE format cross section libraries if the user has not specified the
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<cross_sections> tag in
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.I settings.xml\fP.
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.SH LICENSE
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Copyright \(co 2011-2015 Massachusetts Institute of Technology.
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Copyright \(co 2011-2016 Massachusetts Institute of Technology.
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.PP
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Permission is hereby granted, free of charge, to any person obtaining a copy of
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this software and associated documentation files (the "Software"), to deal in
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2
setup.py
2
setup.py
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@ -9,7 +9,7 @@ except ImportError:
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have_setuptools = False
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kwargs = {'name': 'openmc',
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'version': '0.7.1',
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'version': '0.8.0',
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'packages': ['openmc', 'openmc.data', 'openmc.mgxs', 'openmc.model',
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'openmc.stats'],
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'scripts': glob.glob('scripts/openmc-*'),
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@ -7,8 +7,8 @@ module constants
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! OpenMC major, minor, and release numbers
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integer, parameter :: VERSION_MAJOR = 0
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integer, parameter :: VERSION_MINOR = 7
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integer, parameter :: VERSION_RELEASE = 1
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integer, parameter :: VERSION_MINOR = 8
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integer, parameter :: VERSION_RELEASE = 0
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! Revision numbers for binary files
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integer, parameter :: REVISION_STATEPOINT = 15
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