diff --git a/docs/source/conf.py b/docs/source/conf.py index 38661cdb37..cb43079e37 100644 --- a/docs/source/conf.py +++ b/docs/source/conf.py @@ -69,9 +69,9 @@ copyright = u'2011-2016, Massachusetts Institute of Technology' # built documents. # # The short X.Y version. -version = "0.7" +version = "0.8" # The full version, including alpha/beta/rc tags. -release = "0.7.1" +release = "0.8.0" # The language for content autogenerated by Sphinx. Refer to documentation # for a list of supported languages. diff --git a/docs/source/methods/geometry.rst b/docs/source/methods/geometry.rst index bcd568ca3a..c689883d08 100644 --- a/docs/source/methods/geometry.rst +++ b/docs/source/methods/geometry.rst @@ -205,7 +205,7 @@ traveling in its current direction, it will not hit the surface. The complete derivation for different types of surfaces used in OpenMC will be presented in the following sections. -Since :math:f(x,y,z)` in general is quadratic in :math:`x`, :math:`y`, and +Since :math:`f(x,y,z)` in general is quadratic in :math:`x`, :math:`y`, and :math:`z`, this implies that :math:`f(x_0 + du_0, y + dv_0, z + dw_0)` is quadratic in :math:`d`. Thus we expect at most two real solutions to :eq:`dist-to-boundary-1`. If no solutions to :eq:`dist-to-boundary-1` exist or diff --git a/docs/source/releasenotes.rst b/docs/source/releasenotes.rst index 65309fd70a..3b96be7f8f 100644 --- a/docs/source/releasenotes.rst +++ b/docs/source/releasenotes.rst @@ -1,78 +1,83 @@ .. _releasenotes: ============================== -Release Notes for OpenMC 0.7.1 +Release Notes for OpenMC 0.8.0 ============================== -This release of OpenMC provides some substantial improvements over version -0.7.0. Non-simple cell regions can now be defined through the ``|`` (union) and -``~`` (complement) operators. Similar changes in the Python API also allow -complex cell regions to be defined. A true secondary particle bank now exists; -this is crucial for photon transport (to be added in the next minor release). A -rich API for multi-group cross section generation has been added via the -``openmc.mgxs`` Python module. +This release of OpenMC includes a few new major features including the +capability to perform neutron transport with multi-group cross section data as +well as experimental support for the windowed multipole method being developed +at MIT. Source sampling options have also been expanded significantly, with the +option to supply arbitrary tabular and discrete distributions for energy, angle, +and spatial coordinates. -Various improvements to tallies have also been made. It is now possible to -explicitly specify that a collision estimator be used in a tally. A new -``delayedgroup`` filter and ``delayed-nu-fission`` score allow a user to obtain -delayed fission neutron production rates filtered by delayed group. Finally, the -new ``inverse-velocity`` score may be useful for calculating kinetics -parameters. +The Python API has been significantly restructured in this release compared to +version 0.7.1. Any scripts written based on the version 0.7.1 API will likely +need to be rewritten. Some of the most visible changes include the following: -.. caution:: In previous versions, depending on how OpenMC was compiled binary - output was either given in HDF5 or a flat binary format. With this - version, all binary output is now HDF5 which means you **must** - have HDF5 in order to install OpenMC. Please consult the user's - guide for instructions on how to compile with HDF5. +- ``SettingsFile`` is now ``Settings``, ``MaterialsFile`` is now ``Materials``, + and ``TalliesFile`` is now ``Tallies``. +- The ``GeometryFile`` class no longer exists and is replaced by the + ``Geometry`` class which now has an ``export_to_xml()`` method. +- Source distributions are defined using the ``Source`` class and assigned to + the ``Settings.source`` property. +- The ``Executor`` class no longer exists and is replaced by ``openmc.run()`` + and ``openmc.plot_geometry()`` functions. + +The Python API documentation has also been significantly expanded. ------------------- System Requirements ------------------- There are no special requirements for running the OpenMC code. As of this -release, OpenMC has been tested on a variety of Linux distributions, Mac OS X, -and Microsoft Windows 7. Memory requirements will vary depending on the size of -the problem at hand (mostly on the number of nuclides in the problem). +release, OpenMC has been tested on a variety of Linux distributions and Mac +OS X. Numerous users have reported working builds on Microsoft Windows, but your +mileage may vary. Memory requirements will vary depending on the size of the +problem at hand (mostly on the number of nuclides and tallies in the problem). ------------ New Features ------------ -- Support for complex cell regions (union and complement operators) -- Generic quadric surface type -- Improved handling of secondary particles -- Binary output is now solely HDF5 -- ``openmc.mgxs`` Python module enabling multi-group cross section generation -- Collision estimator for tallies -- Delayed fission neutron production tallies with ability to filter by delayed - group -- Inverse velocity tally score -- Performance improvements for binary search -- Performance improvements for reaction rate tallies +- Multi-group mode +- Vast improvements to the Python API +- Experimental windowed multipole capability +- Periodic boundary conditions +- Expanded source sampling options +- Distributed materials +- Subcritical multiplication support +- Improved method for reproducible URR table sampling +- Refactor of continuous-energy reaction data +- Improved documentation and new Jupyter notebooks --------- Bug Fixes --------- -- 299322_: Bug with material filter when void material present -- d74840_: Fix triggers on tallies with multiple filters -- c29a81_: Correctly handle maximum transport energy -- 3edc23_: Fixes in the nu-scatter score -- 629e3b_: Assume unspecified surface coefficients are zero in Python API -- 5dbe8b_: Fix energy filters for openmc-plot-mesh-tally -- ff66f4_: Fixes in the openmc-plot-mesh-tally script -- 441fd4_: Fix bug in kappa-fission score -- 7e5974_: Allow fixed source simulations from Python API +- 70daa7_: Make sure MT=3 cross section is not used +- 40b05f_: Ensure source bank is resampled for fixed source runs +- 9586ed_: Fix two hexagonal lattice bugs +- a855e8_: Make sure graphite models don't error out on max events +- 7294a1_: Fix incorrect check on cmfd.xml +- 12f246_: Ensure number of realizations is written to statepoint +- 0227f4_: Fix bug when sampling multiple energy distributions +- 51deaa_: Prevent segfault when user specifies '18' on tally scores +- fed74b_: Prevent duplicate tally scores +- 8467ae_: Better threshold for allowable lost particles +- 493c6f_: Fix type of return argument for h5pget_driver_f -.. _299322: https://github.com/mit-crpg/openmc/commit/299322 -.. _d74840: https://github.com/mit-crpg/openmc/commit/d74840 -.. _c29a81: https://github.com/mit-crpg/openmc/commit/c29a81 -.. _3edc23: https://github.com/mit-crpg/openmc/commit/3edc23 -.. _629e3b: https://github.com/mit-crpg/openmc/commit/629e3b -.. _5dbe8b: https://github.com/mit-crpg/openmc/commit/5dbe8b -.. _ff66f4: https://github.com/mit-crpg/openmc/commit/ff66f4 -.. _441fd4: https://github.com/mit-crpg/openmc/commit/441fd4 -.. _7e5974: https://github.com/mit-crpg/openmc/commit/7e5974 +.. _70daa7: https://github.com/mit-crpg/openmc/commit/70daa7 +.. _40b05f: https://github.com/mit-crpg/openmc/commit/40b05f +.. _9586ed: https://github.com/mit-crpg/openmc/commit/9586ed +.. _a855e8: https://github.com/mit-crpg/openmc/commit/a855e8 +.. _7294a1: https://github.com/mit-crpg/openmc/commit/7294a1 +.. _12f246: https://github.com/mit-crpg/openmc/commit/12f246 +.. _0227f4: https://github.com/mit-crpg/openmc/commit/0227f4 +.. _51deaa: https://github.com/mit-crpg/openmc/commit/51deaa +.. _fed74b: https://github.com/mit-crpg/openmc/commit/fed74b +.. _8467ae: https://github.com/mit-crpg/openmc/commit/8467ae +.. _493c6f: https://github.com/mit-crpg/openmc/commit/493c6f ------------ Contributors @@ -81,11 +86,11 @@ Contributors This release contains new contributions from the following people: - `Will Boyd `_ -- `Sterling Harper `_ -- `Bryan Herman `_ +- `Derek Gaston `_ +- `Sterling Harper `_ - `Colin Josey `_ +- `Jingang Liang `_ - `Adam Nelson `_ - `Paul Romano `_ - `Kelly Rowland `_ - `Sam Shaner `_ -- `Jon Walsh `_ diff --git a/man/man1/openmc.1 b/man/man1/openmc.1 index 102adfbdc3..e69360a7c1 100644 --- a/man/man1/openmc.1 +++ b/man/man1/openmc.1 @@ -46,7 +46,7 @@ to locate ACE format cross section libraries if the user has not specified the tag in .I settings.xml\fP. .SH LICENSE -Copyright \(co 2011-2015 Massachusetts Institute of Technology. +Copyright \(co 2011-2016 Massachusetts Institute of Technology. .PP Permission is hereby granted, free of charge, to any person obtaining a copy of this software and associated documentation files (the "Software"), to deal in diff --git a/setup.py b/setup.py index a842a1c3ae..393f40bd35 100644 --- a/setup.py +++ b/setup.py @@ -9,7 +9,7 @@ except ImportError: have_setuptools = False kwargs = {'name': 'openmc', - 'version': '0.7.1', + 'version': '0.8.0', 'packages': ['openmc', 'openmc.data', 'openmc.mgxs', 'openmc.model', 'openmc.stats'], 'scripts': glob.glob('scripts/openmc-*'), diff --git a/src/constants.F90 b/src/constants.F90 index b3e5ed89b1..127b4507fc 100644 --- a/src/constants.F90 +++ b/src/constants.F90 @@ -7,8 +7,8 @@ module constants ! OpenMC major, minor, and release numbers integer, parameter :: VERSION_MAJOR = 0 - integer, parameter :: VERSION_MINOR = 7 - integer, parameter :: VERSION_RELEASE = 1 + integer, parameter :: VERSION_MINOR = 8 + integer, parameter :: VERSION_RELEASE = 0 ! Revision numbers for binary files integer, parameter :: REVISION_STATEPOINT = 15