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Increment version number and add release notes
This commit is contained in:
Paul Romano
parent
df0b28a50d
commit
f5cc7994f7
4 changed files with 112 additions and 56 deletions
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@ -74,9 +74,9 @@ copyright = u'2011-2017, 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 = "0.8"
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version = "0.9"
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# The full version, including alpha/beta/rc tags.
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release = "0.8.0"
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release = "0.9.0"
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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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@ -1,30 +1,59 @@
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.. _releasenotes:
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==============================
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Release Notes for OpenMC 0.8.0
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Release Notes for OpenMC 0.9.0
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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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.. currentmodule:: openmc
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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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This release of OpenMC is the first release to use a new native HDF5 cross
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section format rather than ACE format cross sections. Other significant new
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features include a nuclear data interface in the Python API (:mod:`openmc.data`)
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a stochastic volume calculation capability, a random sphere packing algorithm
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that can handle packing fractions up to 60%, and a new XML parser with
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significantly better performance than the parser used previously.
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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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.. caution:: With the new cross section format, the default energy units are now
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**electronvolts (eV)** rather than megaelectronvolts (MeV)! If you
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are specifying an energy filter for a tally, make sure you use
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units of eV now.
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The Python API documentation has also been significantly expanded.
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The Python API continues to improve over time; several backwards incompatible
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changes were made in the API which users of previous versions should take note
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of:
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- Each type of tally filter is now specified with a separate class. For example::
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energy_filter = openmc.EnergyFilter([0.0, 0.625, 4.0, 1.0e6, 20.0e6])
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- Several attributes of the :class:`Plot` class have changed (``color`` ->
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``color_by`` and ``col_spec`` > ``colors``). :attr:`Plot.colors` now accepts a
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dictionary mapping :class:`Cell` or :class:`Material` instances to RGB
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3-tuples or string colors names, e.g.::
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plot.colors = {
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fuel: 'yellow',
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water: 'blue'
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}
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- ``make_hexagon_region`` is now :func:`get_hexagonal_prism`
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- Several changes in :class:`Settings` attributes:
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- ``weight`` is now set as ``Settings.cutoff['weight']``
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- Shannon entropy is now specified by passing a :class:`openmc.Mesh` to
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:attr:`Settings.entropy_mesh`
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- Uniform fission site method is now specified by passing a
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:class:`openmc.Mesh` to :attr:`Settings.ufs_mesh`
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- All ``sourcepoint_*`` options are now specified in a
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:attr:`Settings.sourcepoint` dictionary
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- Resonance scattering method is now specified as a dictionary in
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:attr:`Settings.resonance_scattering`
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- Multipole is now turned on by setting ``Settings.temperature['multipole'] =
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True``
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- The ``output_path`` attribute is now ``Settings.output['path']``
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- All the ``openmc.mgxs.Nu*`` classes are gone. Instead, a ``nu`` argument was
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added to the constructor of the corresponding classes.
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-------------------
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System Requirements
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@ -40,44 +69,69 @@ problem at hand (mostly on the number of nuclides and tallies in the problem).
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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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- Stochastic volume calculations
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- Multi-delayed group cross section generation
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- Ability to calculate multi-group cross sections over meshes
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- Temperature interpolation on cross section data
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- Nuclear data interface in Python API, :mod:`openmc.data`
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- Allow cutoff energy via :attr:`Settings.cutoff`
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- Ability to define fuel by enrichment (see :meth:`Material.add_element`)
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- Random sphere packing for TRISO particle generation,
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:func:`openmc.model.pack_trisos`
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- Critical eigenvalue search, :func:`openmc.search_for_keff`
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- Model container, :class:`openmc.model.Model`
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- In-line plotting in Jupyter, :func:`openmc.plot_inline`
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- Energy function tally filters, :class:`openmc.EnergyFunctionFilter`
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- Replaced FoX XML parser with `pugixml <http://pugixml.org/>`_
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- Cell/material instance counting, :meth:`Geometry.determine_paths`
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- Differential tallies (see :class:`openmc.TallyDerivative`)
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- Consistent multi-group scattering matrices
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- Improved documentation and new Jupyter notebooks
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- OpenMOC compatibility module, :mod:`openmc.openmoc_compatible`
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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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- c5df6c_: Fix mesh filter max iterator check
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- 1cfa39_: Reject external source only if 95% of sites are rejected
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- 335359_: Fix bug in plotting meshlines
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- 17c678_: Make sure system_clock uses high-resolution timer
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- 23ec0b_: Fix use of S(a,b) with multipole data
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- 7eefb7_: Fix several bugs in tally module
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- 7880d4_: Allow plotting calculation with no boundary conditions
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- ad2d9f_: Fix filter weight missing when scoring all nuclides
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- 59fdca_: Fix use of source files for fixed source calculations
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- 9eff5b_: Fix thermal scattering bugs
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- 7848a9_: Fix combined k-eff estimator producing NaN
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- f139ce_: Fix printing bug for tallies with AggregateNuclide
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- b8ddfa_: Bugfix for short tracks near tally mesh edges
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- ec3cfb_: Fix inconsistency in filter weights
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- 5e9b06_: Fix XML representation for verbosity
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- c39990_: Fix bug tallying reaction rates with multipole on
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- c6b67e_: Fix fissionable source sampling bug
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- 489540_: Check for void materials in tracklength tallies
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- f0214f_: Fixes/improvements to the ARES algorithm
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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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.. _c5df6c: https://github.com/mit-crpg/openmc/commit/c5df6c
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.. _1cfa39: https://github.com/mit-crpg/openmc/commit/1cfa39
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.. _335359: https://github.com/mit-crpg/openmc/commit/335359
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.. _17c678: https://github.com/mit-crpg/openmc/commit/17c678
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.. _23ec0b: https://github.com/mit-crpg/openmc/commit/23ec0b
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.. _7eefb7: https://github.com/mit-crpg/openmc/commit/7eefb7
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.. _7880d4: https://github.com/mit-crpg/openmc/commit/7880d4
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.. _ad2d9f: https://github.com/mit-crpg/openmc/commit/ad2d9f
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.. _59fdca: https://github.com/mit-crpg/openmc/commit/59fdca
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.. _9eff5b: https://github.com/mit-crpg/openmc/commit/9eff5b
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.. _7848a9: https://github.com/mit-crpg/openmc/commit/7848a9
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.. _f139ce: https://github.com/mit-crpg/openmc/commit/f139ce
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.. _b8ddfa: https://github.com/mit-crpg/openmc/commit/b8ddfa
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.. _ec3cfb: https://github.com/mit-crpg/openmc/commit/ec3cfb
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.. _5e9b06: https://github.com/mit-crpg/openmc/commit/5e9b06
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.. _c39990: https://github.com/mit-crpg/openmc/commit/c39990
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.. _c6b67e: https://github.com/mit-crpg/openmc/commit/c6b67e
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.. _489540: https://github.com/mit-crpg/openmc/commit/489540
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.. _f0214f: https://github.com/mit-crpg/openmc/commit/f0214f
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------------
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Contributors
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@ -86,11 +140,13 @@ 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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- `Derek Gaston <friedmud@gmail.com>`_
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- `Sterling Harper <sterlingmharper@gmail.com>`_
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- `Qingming He <906459647@qq.com>`_
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- `Colin Josey <cjosey@mit.edu>`_
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- `Travis Labossiere-Hickman <tjlaboss@mit.edu>`_
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- `Jingang Liang <liangjg2008@gmail.com>`_
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- `Amanda Lund <alund@anl.gov>`_
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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 <jonathan.a.walsh@gmail.com>`_
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2
setup.py
2
setup.py
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@ -16,7 +16,7 @@ except ImportError:
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have_cython = False
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kwargs = {'name': 'openmc',
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'version': '0.8.0',
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'version': '0.9.0',
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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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@ -7,7 +7,7 @@ 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 = 8
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integer, parameter :: VERSION_MINOR = 9
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integer, parameter :: VERSION_RELEASE = 0
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integer, parameter :: &
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VERSION(3) = [VERSION_MAJOR, VERSION_MINOR, VERSION_RELEASE]
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