From 36f633c453205f863ba2881692c3b0eb45d5fdc6 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Fri, 30 Oct 2015 08:13:20 -0500 Subject: [PATCH] Incremented version. Added release notes for 0.7.1. --- docs/source/conf.py | 2 +- docs/source/releasenotes.rst | 83 +++++++++++++++++++++++------------- setup.py | 2 +- src/constants.F90 | 2 +- 4 files changed, 56 insertions(+), 33 deletions(-) diff --git a/docs/source/conf.py b/docs/source/conf.py index 79a7604e39..118ff2c03b 100644 --- a/docs/source/conf.py +++ b/docs/source/conf.py @@ -55,7 +55,7 @@ copyright = u'2011-2015, Massachusetts Institute of Technology' # The short X.Y version. version = "0.7" # The full version, including alpha/beta/rc tags. -release = "0.7.0" +release = "0.7.1" # The language for content autogenerated by Sphinx. Refer to documentation # for a list of supported languages. diff --git a/docs/source/releasenotes.rst b/docs/source/releasenotes.rst index dffc17201f..7320781e2b 100644 --- a/docs/source/releasenotes.rst +++ b/docs/source/releasenotes.rst @@ -1,9 +1,30 @@ .. _releasenotes: ============================== -Release Notes for OpenMC 0.7.0 +Release Notes for OpenMC 0.7.1 ============================== +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. + +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. + +.. 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. + ------------------- System Requirements ------------------- @@ -17,36 +38,41 @@ the problem at hand (mostly on the number of nuclides in the problem). New Features ------------ -- Complete Python API -- Python 3 compatability for all scripts -- All scripts consistently named openmc-* and installed together -- New 'distribcell' tally filter for repeated cells -- Ability to specify outer lattice universe -- XML input validation utility (openmc-validate-xml) -- Support for hexagonal lattices -- Material union energy grid method -- Tally triggers -- Remove dependence on PETSc -- Significant OpenMP performance improvements -- Support for Fortran 2008 MPI interface -- Use of Travis CI for continuous integration -- Simplifications and improvements to test suite +- 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 --------- Bug Fixes --------- -- b5f712_: Fix bug in spherical harmonics tallies -- e6675b_: Ensure all constants are double precision -- 04e2c1_: Fix potential bug in sample_nuclide routine -- 6121d9_: Fix bugs related to particle track files -- 2f0e89_: Fixes for nuclide specification in tallies +- 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 -.. _b5f712: https://github.com/mit-crpg/openmc/commit/b5f712 -.. _e6675b: https://github.com/mit-crpg/openmc/commit/e6675b -.. _04e2c1: https://github.com/mit-crpg/openmc/commit/04e2c1 -.. _6121d9: https://github.com/mit-crpg/openmc/commit/6121d9 -.. _2f0e89: https://github.com/mit-crpg/openmc/commit/2f0e89 +.. _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 ------------ Contributors @@ -55,13 +81,10 @@ Contributors This release contains new contributions from the following people: - `Will Boyd `_ -- `Matt Ellis `_ - `Sterling Harper `_ -- `Bryan Herman `_ -- `Nicholas Horelik `_ - `Colin Josey `_ -- `William Lyu `_ - `Adam Nelson `_ - `Paul Romano `_ -- `Anthony Scopatz `_ +- `Kelly Rowland `_ +- `Sam Shaner `_ - `Jon Walsh `_ diff --git a/setup.py b/setup.py index 0c3d5c116f..907d80e31b 100644 --- a/setup.py +++ b/setup.py @@ -10,7 +10,7 @@ except ImportError: have_setuptools = False kwargs = {'name': 'openmc', - 'version': '0.7.0', + 'version': '0.7.1', 'packages': ['openmc', 'openmc.mgxs'], 'scripts': glob.glob('scripts/openmc-*'), diff --git a/src/constants.F90 b/src/constants.F90 index 375c517e76..ba77f35aba 100644 --- a/src/constants.F90 +++ b/src/constants.F90 @@ -8,7 +8,7 @@ module constants ! OpenMC major, minor, and release numbers integer, parameter :: VERSION_MAJOR = 0 integer, parameter :: VERSION_MINOR = 7 - integer, parameter :: VERSION_RELEASE = 0 + integer, parameter :: VERSION_RELEASE = 1 ! Revision numbers for binary files integer, parameter :: REVISION_STATEPOINT = 14