From 93e043e630d640616efeff9dbac97cd7a41762bc Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 29 May 2019 07:06:10 -0500 Subject: [PATCH] Add old release notes and current in new directory in docs/ --- docs/source/index.rst | 2 +- .../0.10.0.rst} | 2 - docs/source/releasenotes/0.4.0.rst | 36 +++++ docs/source/releasenotes/0.4.1.rst | 55 +++++++ docs/source/releasenotes/0.4.2.rst | 56 +++++++ docs/source/releasenotes/0.4.3.rst | 53 +++++++ docs/source/releasenotes/0.4.4.rst | 45 ++++++ docs/source/releasenotes/0.5.0.rst | 52 ++++++ docs/source/releasenotes/0.5.1.rst | 45 ++++++ docs/source/releasenotes/0.5.2.rst | 57 +++++++ docs/source/releasenotes/0.5.3.rst | 49 ++++++ docs/source/releasenotes/0.5.4.rst | 64 ++++++++ docs/source/releasenotes/0.6.0.rst | 59 +++++++ docs/source/releasenotes/0.6.1.rst | 65 ++++++++ docs/source/releasenotes/0.6.2.rst | 58 +++++++ docs/source/releasenotes/0.7.0.rst | 65 ++++++++ docs/source/releasenotes/0.7.1.rst | 89 +++++++++++ docs/source/releasenotes/0.8.0.rst | 94 +++++++++++ docs/source/releasenotes/0.9.0.rst | 150 ++++++++++++++++++ docs/source/releasenotes/index.rst | 27 ++++ 20 files changed, 1120 insertions(+), 3 deletions(-) rename docs/source/{releasenotes.rst => releasenotes/0.10.0.rst} (99%) create mode 100644 docs/source/releasenotes/0.4.0.rst create mode 100644 docs/source/releasenotes/0.4.1.rst create mode 100644 docs/source/releasenotes/0.4.2.rst create mode 100644 docs/source/releasenotes/0.4.3.rst create mode 100644 docs/source/releasenotes/0.4.4.rst create mode 100644 docs/source/releasenotes/0.5.0.rst create mode 100644 docs/source/releasenotes/0.5.1.rst create mode 100644 docs/source/releasenotes/0.5.2.rst create mode 100644 docs/source/releasenotes/0.5.3.rst create mode 100644 docs/source/releasenotes/0.5.4.rst create mode 100644 docs/source/releasenotes/0.6.0.rst create mode 100644 docs/source/releasenotes/0.6.1.rst create mode 100644 docs/source/releasenotes/0.6.2.rst create mode 100644 docs/source/releasenotes/0.7.0.rst create mode 100644 docs/source/releasenotes/0.7.1.rst create mode 100644 docs/source/releasenotes/0.8.0.rst create mode 100644 docs/source/releasenotes/0.9.0.rst create mode 100644 docs/source/releasenotes/index.rst diff --git a/docs/source/index.rst b/docs/source/index.rst index 4071b9794..5500890e2 100644 --- a/docs/source/index.rst +++ b/docs/source/index.rst @@ -35,7 +35,7 @@ list `_. quickinstall examples/index - releasenotes + releasenotes/index methods/index usersguide/index devguide/index diff --git a/docs/source/releasenotes.rst b/docs/source/releasenotes/0.10.0.rst similarity index 99% rename from docs/source/releasenotes.rst rename to docs/source/releasenotes/0.10.0.rst index d5ea6c58c..86eb8f1f6 100644 --- a/docs/source/releasenotes.rst +++ b/docs/source/releasenotes/0.10.0.rst @@ -1,5 +1,3 @@ -.. _releasenotes: - =============================== Release Notes for OpenMC 0.10.0 =============================== diff --git a/docs/source/releasenotes/0.4.0.rst b/docs/source/releasenotes/0.4.0.rst new file mode 100644 index 000000000..3e0a444e3 --- /dev/null +++ b/docs/source/releasenotes/0.4.0.rst @@ -0,0 +1,36 @@ +.. _notes_0.4.0: + +============================== +Release Notes for OpenMC 0.4.0 +============================== + +------------------- +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 as well as +Mac OS X. However, it has not been tested yet on any releases of Microsoft +Windows. Memory requirements will vary depending on the size of the problem at +hand (mostly on the number of nuclides in the problem). + +------------ +New Features +------------ + +- The probability table method for treatment of energy self-shielding in the + unresolved resonance range has been implemented and is now turned on by + default. +- Calculation of Shannon entropy for assessing convergence of the fission source + distribution. +- Ability to compile with the PGI Fortran compiler. +- Ability to run on IBM BlueGene/P machines. +- Completely rewrote how nested universes are handled. Geometry is now much more + robust. + +--------- +Bug Fixes +--------- + +- Many geometry errors have been fixed. The Monte Carlo performance benchmark + can now be successfully run in OpenMC. diff --git a/docs/source/releasenotes/0.4.1.rst b/docs/source/releasenotes/0.4.1.rst new file mode 100644 index 000000000..2492f23a9 --- /dev/null +++ b/docs/source/releasenotes/0.4.1.rst @@ -0,0 +1,55 @@ +.. _notes_0.4.1: + +============================== +Release Notes for OpenMC 0.4.1 +============================== + +------------------- +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 as well as +Mac OS X. However, it has not been tested yet on any releases of Microsoft +Windows. Memory requirements will vary depending on the size of the problem at +hand (mostly on the number of nuclides in the problem). + +------------ +New Features +------------ + +- A batching method has been implemented so that statistics can be calculated + based on multiple generations instead of a single generation. This can help to + overcome problems with underpredicted variance in problems where there is + correlation between successive fission source iterations. +- Users now have the option to select a non-unionized energy grid for problems + with many nuclides where the use of a unionized grid is not feasible. +- Improved plotting capability (Nick Horelik). The plotting input is now in + ``plots.xml`` instead of ``plot.xml``. +- Added multiple estimators for k-effective and added a global tally for + leakage. +- Moved cross section-related output into cross_sections.out. +- Improved timing capabilities. +- Can now use more than 2**31 - 1 particles per generation. +- Improved fission bank synchronization method. This also necessitated changing + the source bank to be of type Bank rather than of type Particle. +- Added HDF5 output (not complete yet). +- Major changes to tally implementation. + +--------- +Bug Fixes +--------- + +- `b206a8`_: Fixed subtle error in the sampling of energy distributions. +- `800742`_: Fixed error in sampling of angle and rotating angles. +- `a07c08`_: Fixed bug in linear-linear interpolation during sampling energy. +- `a75283`_: Fixed energy and energyout tally filters to support many bins. +- `95cfac`_: Fixed error in cell neighbor searches. +- `83a803`_: Fixed bug related to probability tables. + +.. _b206a8: https://github.com/mit-crpg/openmc/commit/b206a8 +.. _800742: https://github.com/mit-crpg/openmc/commit/800742 +.. _a07c08: https://github.com/mit-crpg/openmc/commit/a07c08 +.. _a75283: https://github.com/mit-crpg/openmc/commit/a75283 +.. _95cfac: https://github.com/mit-crpg/openmc/commit/95cfac +.. _83a803: https://github.com/mit-crpg/openmc/commit/83a803 diff --git a/docs/source/releasenotes/0.4.2.rst b/docs/source/releasenotes/0.4.2.rst new file mode 100644 index 000000000..0ca5287a1 --- /dev/null +++ b/docs/source/releasenotes/0.4.2.rst @@ -0,0 +1,56 @@ +.. _notes_0.4.2: + +============================== +Release Notes for OpenMC 0.4.2 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Ability to specify void materials. +- Option to not reduce tallies across processors at end of each batch. +- Uniform fission site method for reducing variance on local tallies. +- Reading/writing binary source files. +- Added more messages for or high verbosity. +- Estimator for diffusion coefficient. +- Ability to specify 'point' source type. +- Ability to change random number seed. +- Users can now specify units='sum' on a tag. This tells the code that + the total material density is the sum of the atom fractions listed for each + nuclide on the material. + +--------- +Bug Fixes +--------- + +- a27f8f_: Fixed runtime error bug when using Intel compiler with DEBUG on. +- afe121_: Fixed minor bug in fission bank algorithms. +- e0968e_: Force re-evaluation of cross-sections when each particle is born. +- 298db8_: Fixed bug in surface currents when using energy-in filter. +- 2f3bbe_: Fixed subtle bug in S(a,b) cross section calculation. +- 671f30_: Fixed surface currents on mesh not encompassing geometry. +- b2c40e_: Fixed bug in incoming energy filter for track-length tallies. +- 5524fd_: Mesh filter now works with track-length tallies. +- d050c7_: Added Bessel's correction to make estimate of variance unbiased. +- 2a5b9c_: Fixed regression in plotting. + +.. _a27f8f: https://github.com/mit-crpg/openmc/commit/a27f8f +.. _afe121: https://github.com/mit-crpg/openmc/commit/afe121 +.. _e0968e: https://github.com/mit-crpg/openmc/commit/e0968e +.. _298db8: https://github.com/mit-crpg/openmc/commit/298db8 +.. _2f3bbe: https://github.com/mit-crpg/openmc/commit/2f3bbe +.. _671f30: https://github.com/mit-crpg/openmc/commit/671f30 +.. _b2c40e: https://github.com/mit-crpg/openmc/commit/b2c40e +.. _5524fd: https://github.com/mit-crpg/openmc/commit/5524fd +.. _d050c7: https://github.com/mit-crpg/openmc/commit/d050c7 +.. _2a5b9c: https://github.com/mit-crpg/openmc/commit/2a5b9c diff --git a/docs/source/releasenotes/0.4.3.rst b/docs/source/releasenotes/0.4.3.rst new file mode 100644 index 000000000..fce7a7da3 --- /dev/null +++ b/docs/source/releasenotes/0.4.3.rst @@ -0,0 +1,53 @@ +.. _notes_0.4.3: + +============================== +Release Notes for OpenMC 0.4.3 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Option to report confidence intervals for tally results. +- Rotation and translation for filled cells. +- Ability to explicitly specify for tallies. +- Ability to store state points and use them to restart runs. +- Fixed source calculations (no subcritical multiplication however). +- Expanded options for external source distribution. +- Ability to tally reaction rates for individual nuclides within a material. +- Reduced memory usage by removing redundant storage or some cross-sections. +- 3bd35b_: Log-log interpolation for URR probability tables. +- Support to specify labels on tallies (nelsonag_). + +--------- +Bug Fixes +--------- + +- 33f29a_: Handle negative values in probability table. +- 1c472d_: Fixed survival biasing with probability tables. +- 3c6e80_: Fixed writing tallies with no filters. +- 460ef1_: Invalid results for duplicate tallies. +- 0069d5_: Fixed bug with 0 inactive batches. +- 7af2cf_: Fixed bug in score_analog_tallies. +- 85a60e_: Pick closest angular distribution for law 61. +- 3212f5_: Fixed issue with blank line at beginning of XML files. + +.. _nelsonag: https://github.com/nelsonag +.. _33f29a: https://github.com/mit-crpg/openmc/commit/33f29a +.. _1c472d: https://github.com/mit-crpg/openmc/commit/1c472d +.. _3c6e80: https://github.com/mit-crpg/openmc/commit/3c6e80 +.. _3bd35b: https://github.com/mit-crpg/openmc/commit/3bd35b +.. _0069d5: https://github.com/mit-crpg/openmc/commit/0069d5 +.. _7af2cf: https://github.com/mit-crpg/openmc/commit/7af2cf +.. _460ef1: https://github.com/mit-crpg/openmc/commit/460ef1 +.. _85a60e: https://github.com/mit-crpg/openmc/commit/85a60e +.. _3212f5: https://github.com/mit-crpg/openmc/commit/3212f5 diff --git a/docs/source/releasenotes/0.4.4.rst b/docs/source/releasenotes/0.4.4.rst new file mode 100644 index 000000000..55a0c3f6f --- /dev/null +++ b/docs/source/releasenotes/0.4.4.rst @@ -0,0 +1,45 @@ +.. _notes_0.4.4: + +============================== +Release Notes for OpenMC 0.4.4 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Ability to write state points when using . +- Real-time XML validation in GNU Emacs with RELAX NG schemata. +- Writing state points every n batches with +- Suppress creation of summary.out and cross_sections.out by default with option + to turn them on with tag in settings.xml file. +- Ability to create HDF5 state points. +- Binary source file is now part of state point file by default. +- Enhanced state point usage and added state point Python scripts. +- Turning confidence intervals on affects k-effective. +- Option to specify for tally meshes. + +--------- +Bug Fixes +--------- + +- 4654ee_: Fixed plotting with void cells. +- 7ee461_: Fixed bug with multi-line input using type='word'. +- 792eb3_: Fixed degrees of freedom for confidence intervals. +- 7fd617_: Fixed bug with restart runs in parallel. +- dc4a8f_: Fixed bug with fixed source restart runs. + +.. _4654ee: https://github.com/mit-crpg/openmc/commit/4654ee +.. _7ee461: https://github.com/mit-crpg/openmc/commit/7ee461 +.. _792eb3: https://github.com/mit-crpg/openmc/commit/792eb3 +.. _7fd617: https://github.com/mit-crpg/openmc/commit/7fd617 +.. _dc4a8f: https://github.com/mit-crpg/openmc/commit/dc4a8f diff --git a/docs/source/releasenotes/0.5.0.rst b/docs/source/releasenotes/0.5.0.rst new file mode 100644 index 000000000..16be1b063 --- /dev/null +++ b/docs/source/releasenotes/0.5.0.rst @@ -0,0 +1,52 @@ +.. _notes_0.5.0: + +============================== +Release Notes for OpenMC 0.5.0 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- All user input options that formerly accepted "off" or "on" should now be + "false" or "true" (the proper XML schema datatype). +- The element is deprecated and was replaced with . +- Added 'events' score that returns number of events that scored to a tally. +- Restructured tally filter implementation and user input. +- Source convergence acceleration via CMFD (implemented with PETSc). +- Ability to read source files in parallel when number of particles is greater + than that number of source sites. +- Cone surface types. + +--------- +Bug Fixes +--------- + +- 737b90_: Coincident surfaces from separate universes / particle traveling + tangent to a surface. +- a819b4_: Output of surface neighbors in summary.out file. +- b11696_: Reading long attribute lists in XML input. +- 2bd46a_: Search for tallying nuclides when no default_xs specified. +- 7a1f08_: Fix word wrapping when writing messages. +- c0e3ec_: Prevent underflow when compiling with MPI=yes and DEBUG=yes. +- 6f8d9d_: Set default tally labels. +- 6a3a5e_: Fix problem with corner-crossing in lattices. + +.. _737b90: https://github.com/mit-crpg/openmc/commit/737b90 +.. _a819b4: https://github.com/mit-crpg/openmc/commit/a819b4 +.. _b11696: https://github.com/mit-crpg/openmc/commit/b11696 +.. _2bd46a: https://github.com/mit-crpg/openmc/commit/2bd46a +.. _7a1f08: https://github.com/mit-crpg/openmc/commit/7a1f08 +.. _c0e3ec: https://github.com/mit-crpg/openmc/commit/c0e3ec +.. _6f8d9d: https://github.com/mit-crpg/openmc/commit/6f8d9d +.. _6a3a5e: https://github.com/mit-crpg/openmc/commit/6a3a5e + diff --git a/docs/source/releasenotes/0.5.1.rst b/docs/source/releasenotes/0.5.1.rst new file mode 100644 index 000000000..9ba85d304 --- /dev/null +++ b/docs/source/releasenotes/0.5.1.rst @@ -0,0 +1,45 @@ +.. _notes_0.5.1: + +============================== +Release Notes for OpenMC 0.5.1 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Absorption and combined estimators for k-effective. +- Natural elements can now be specified in materials using rather than + . +- Support for multiple S(a,b) tables in a single material (e.g. BeO). +- Test suite using Python nosetests. +- Proper install capability with 'make install'. +- Lattices can now be 2 or 3 dimensions. +- New scatter-PN score type. +- New kappa-fission score type. +- Ability to tally any reaction by specifying MT. + +--------- +Bug Fixes +--------- + +- 94103e_: Two checks for outgoing energy filters. +- e77059_: Fix reaction name for MT=849. +- b0fe88_: Fix distance to surface for cones. +- 63bfd2_: Fix tracklength tallies with cell filter and universes. +- 88daf7_: Fix analog tallies with survival biasing. + +.. _94103e: https://github.com/mit-crpg/openmc/commit/94103e +.. _e77059: https://github.com/mit-crpg/openmc/commit/e77059 +.. _b0fe88: https://github.com/mit-crpg/openmc/commit/b0fe88 +.. _63bfd2: https://github.com/mit-crpg/openmc/commit/63bfd2 +.. _88daf7: https://github.com/mit-crpg/openmc/commit/88daf7 diff --git a/docs/source/releasenotes/0.5.2.rst b/docs/source/releasenotes/0.5.2.rst new file mode 100644 index 000000000..d030615db --- /dev/null +++ b/docs/source/releasenotes/0.5.2.rst @@ -0,0 +1,57 @@ +.. _notes_0.5.2: + +============================== +Release Notes for OpenMC 0.5.2 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Python script for mesh tally plotting +- Isotopic abundances based on IUPAC 2009 when using +- Particle restart files for debugging +- Code will abort after certain number of lost particles (defaults to 10) +- Region outside lattice can be filled with material (void by default) +- 3D voxel plots +- Full HDF5/PHDF5 support (including support in statepoint.py) +- Cell overlap checking with -g command line flag (or when plotting) + +--------- +Bug Fixes +--------- + +- 7632f3_: Fixed bug in statepoint.py for multiple generations per batch. +- f85ac4_: Fix infinite loop bug in error module. +- 49c36b_: Don't convert surface ids if surface filter is for current tallies. +- 5ccc78_: Fix bug in reassignment of bins for mesh filter. +- b1f52f_: Fixed bug in plot color specification. +- eae7e5_: Fixed many memory leaks. +- 10c1cc_: Minor CMFD fixes. +- afdb50_: Add compatibility for XML comments without whitespace. +- a3c593_: Fixed bug in use of free gas scattering for H-1. +- 3a66e3_: Fixed bug in 2D mesh tally implementation. +- ab0793_: Corrected PETSC_NULL references to their correct types. +- 182ebd_: Use analog estimator with energyout filter. + +.. _7632f3: https://github.com/mit-crpg/openmc/commit/7632f3 +.. _f85ac4: https://github.com/mit-crpg/openmc/commit/f85ac4 +.. _49c36b: https://github.com/mit-crpg/openmc/commit/49c36b +.. _5ccc78: https://github.com/mit-crpg/openmc/commit/5ccc78 +.. _b1f52f: https://github.com/mit-crpg/openmc/commit/b1f52f +.. _eae7e5: https://github.com/mit-crpg/openmc/commit/eae7e5 +.. _10c1cc: https://github.com/mit-crpg/openmc/commit/10c1cc +.. _afdb50: https://github.com/mit-crpg/openmc/commit/afdb50 +.. _a3c593: https://github.com/mit-crpg/openmc/commit/a3c593 +.. _3a66e3: https://github.com/mit-crpg/openmc/commit/3a66e3 +.. _ab0793: https://github.com/mit-crpg/openmc/commit/ab0793 +.. _182ebd: https://github.com/mit-crpg/openmc/commit/182ebd diff --git a/docs/source/releasenotes/0.5.3.rst b/docs/source/releasenotes/0.5.3.rst new file mode 100644 index 000000000..6d93f9aec --- /dev/null +++ b/docs/source/releasenotes/0.5.3.rst @@ -0,0 +1,49 @@ +.. _notes_0.5.3: + +============================== +Release Notes for OpenMC 0.5.3 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Output interface enhanced to allow multiple files handles to be opened +- Particle restart file linked to output interface +- Particle restarts and state point restarts are both identified with the -r + command line flag. +- Particle instance no longer global, passed to all physics routines +- Physics routines refactored to rely less on global memory, more arguments + passed in +- CMFD routines refactored and now can compute dominance ratio on the fly +- PETSc 3.4.2 or higher must be used and compiled with fortran datatype support +- Memory leaks fixed except for ones from xml-fortran package +- Test suite enhanced to test output with different compiler options +- Description of OpenMC development workflow added +- OpenMP shared-memory parallelism added +- Special run mode --tallies removed. + +--------- +Bug Fixes +--------- + +- 2b1e8a_: Normalize direction vector after reflecting particle. +- 5853d2_: Set blank default for cross section listing alias. +- e178c7_: Fix infinite loop with words greater than 80 characters in write_message. +- c18a6e_: Check for valid secondary mode on S(a,b) tables. +- 82c456_: Fix bug where last process could have zero particles. + +.. _2b1e8a: https://github.com/mit-crpg/openmc/commit/2b1e8a +.. _5853d2: https://github.com/mit-crpg/openmc/commit/5853d2 +.. _e178c7: https://github.com/mit-crpg/openmc/commit/e178c7 +.. _c18a6e: https://github.com/mit-crpg/openmc/commit/c18a6e +.. _82c456: https://github.com/mit-crpg/openmc/commit/82c456 diff --git a/docs/source/releasenotes/0.5.4.rst b/docs/source/releasenotes/0.5.4.rst new file mode 100644 index 000000000..a69354aa0 --- /dev/null +++ b/docs/source/releasenotes/0.5.4.rst @@ -0,0 +1,64 @@ +.. _notes_0.5.4: + +============================== +Release Notes for OpenMC 0.5.4 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Source sites outside geometry are resampled +- XML-Fortran backend replaced by FoX XML +- Ability to write particle track files +- Handle lost particles more gracefully (via particle track files) +- Multiple random number generator streams +- Mesh tally plotting utility converted to use Tkinter rather than PyQt +- Script added to download ACE data from NNDC +- Mixed ASCII/binary cross_sections.xml now allowed +- Expanded options for writing source bank +- Re-enabled ability to use source file as starting source +- S(a,b) recalculation avoided when same nuclide and S(a,b) table are accessed + +--------- +Bug Fixes +--------- + +- 32c03c_: Check for valid data in cross_sections.xml +- c71ef5_: Fix bug in statepoint.py +- 8884fb_: Check for all ZAIDs for S(a,b) tables +- b38af0_: Fix XML reading on multiple levels of input +- d28750_: Fix bug in convert_xsdir.py +- cf567c_: ENDF/B-VI data checked for compatibility +- 6b9461_: Fix p_valid sampling inside of sample_energy + +.. _32c03c: https://github.com/mit-crpg/openmc/commit/32c03c +.. _c71ef5: https://github.com/mit-crpg/openmc/commit/c71ef5 +.. _8884fb: https://github.com/mit-crpg/openmc/commit/8884fb +.. _b38af0: https://github.com/mit-crpg/openmc/commit/b38af0 +.. _d28750: https://github.com/mit-crpg/openmc/commit/d28750 +.. _cf567c: https://github.com/mit-crpg/openmc/commit/cf567c +.. _6b9461: https://github.com/mit-crpg/openmc/commit/6b9461 + +------------ +Contributors +------------ + +This release contains new contributions from the following people: + +- `Sterling Harper `_ +- `Bryan Herman `_ +- `Nick Horelik `_ +- `Adam Nelson `_ +- `Paul Romano `_ +- `Tuomas Viitanen `_ +- `Jon Walsh `_ diff --git a/docs/source/releasenotes/0.6.0.rst b/docs/source/releasenotes/0.6.0.rst new file mode 100644 index 000000000..3f98c461d --- /dev/null +++ b/docs/source/releasenotes/0.6.0.rst @@ -0,0 +1,59 @@ +.. _notes_0.6.0: + +============================== +Release Notes for OpenMC 0.6.0 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Legendre and spherical harmonic expansion tally scores +- CMake is now default build system +- Regression test suite based on CTests and NNDC cross sections +- FoX is now a git submodule +- Support for older cross sections (e.g. MCNP 66c) +- Progress bar for plots +- Expanded support for natural elements via in settings.xml + +--------- +Bug Fixes +--------- + +- 41f7ca_: Fixed erroneous results from survival biasing +- 038736_: Fix tallies over void materials +- 46f9e8_: Check for negative values in probability tables +- d1ca35_: Fixed sampling of angular distribution +- 0291c0_: Fixed indexing error in plotting +- d7a7d0_: Fix bug with specifying xs attribute +- 85b3cb_: Fix out-of-bounds error with OpenMP threading + +.. _41f7ca: https://github.com/mit-crpg/openmc/commit/41f7ca +.. _038736: https://github.com/mit-crpg/openmc/commit/038736 +.. _46f9e8: https://github.com/mit-crpg/openmc/commit/46f9e8 +.. _d1ca35: https://github.com/mit-crpg/openmc/commit/d1ca35 +.. _0291c0: https://github.com/mit-crpg/openmc/commit/0291c0 +.. _d7a7d0: https://github.com/mit-crpg/openmc/commit/d7a7d0 +.. _85b3cb: https://github.com/mit-crpg/openmc/commit/85b3cb + +------------ +Contributors +------------ + +This release contains new contributions from the following people: + +- `Sterling Harper `_ +- `Bryan Herman `_ +- `Nick Horelik `_ +- `Adam Nelson `_ +- `Paul Romano `_ +- `Jon Walsh `_ diff --git a/docs/source/releasenotes/0.6.1.rst b/docs/source/releasenotes/0.6.1.rst new file mode 100644 index 000000000..71852bd17 --- /dev/null +++ b/docs/source/releasenotes/0.6.1.rst @@ -0,0 +1,65 @@ +.. _notes_0.6.1: + +============================== +Release Notes for OpenMC 0.6.1 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Coarse mesh finite difference (CMFD) acceleration no longer requires PETSc +- Statepoint file numbering is now zero-padded +- Python scripts now compatible with Python 2 or 3 +- Ability to run particle restarts in fixed source calculations +- Capability to filter box source by fissionable materials +- Nuclide/element names are now case insensitive in input files +- Improved treatment of resonance scattering for heavy nuclides + +--------- +Bug Fixes +--------- + +- 03e890_: Check for energy-dependent multiplicities in ACE files +- 4439de_: Fix distance-to-surface calculation for general plane surface +- 5808ed_: Account for differences in URR band probabilities at different energies +- 2e60c0_: Allow zero atom/weight percents in materials +- 3e0870_: Don't use PWD environment variable when setting path to input files +- dc4776_: Handle probability table resampling correctly +- 01178b_: Fix metastables nuclides in NNDC cross_sections.xml file +- 62ec43_: Don't read tallies.xml when OpenMC is run in plotting mode +- 2a95ef_: Prevent segmentation fault on "current" score without mesh filter +- 93e482_: Check for negative values in probability tables + +.. _03e890: https://github.com/mit-crpg/openmc/commit/03e890 +.. _4439de: https://github.com/mit-crpg/openmc/commit/4439de +.. _5808ed: https://github.com/mit-crpg/openmc/commit/5808ed +.. _2e60c0: https://github.com/mit-crpg/openmc/commit/2e60c0 +.. _3e0870: https://github.com/mit-crpg/openmc/commit/3e0870 +.. _dc4776: https://github.com/mit-crpg/openmc/commit/dc4776 +.. _01178b: https://github.com/mit-crpg/openmc/commit/01178b +.. _62ec43: https://github.com/mit-crpg/openmc/commit/62ec43 +.. _2a95ef: https://github.com/mit-crpg/openmc/commit/2a95ef +.. _93e482: https://github.com/mit-crpg/openmc/commit/93e482 + +------------ +Contributors +------------ + +This release contains new contributions from the following people: + +- `Sterling Harper `_ +- `Bryan Herman `_ +- `Adam Nelson `_ +- `Paul Romano `_ +- `Jon Walsh `_ +- `Will Boyd `_ diff --git a/docs/source/releasenotes/0.6.2.rst b/docs/source/releasenotes/0.6.2.rst new file mode 100644 index 000000000..eefc493fc --- /dev/null +++ b/docs/source/releasenotes/0.6.2.rst @@ -0,0 +1,58 @@ +.. _notes_0.6.2: + +============================== +Release Notes for OpenMC 0.6.2 +============================== + +------------------- +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). + +------------ +New Features +------------ + +- Meshline plotting capability +- Support for plotting cells/materials on middle universe levels +- Ability to model cells with no surfaces +- Compatibility with PETSc 3.5 +- Compatability with OpenMPI 1.7/1.8 +- Improved overall performance via logarithmic-mapped energy grid search +- Improved multi-threaded performance with atomic operations +- Support for fixed source problems with fissionable materials + +--------- +Bug Fixes +--------- + +- 26fb93_: Fix problem with -t, --track command-line flag +- 2f07c0_: Improved evaporation spectrum algorithm +- e6abb9_: Fix segfault when tallying in a void material +- 291b45_: Handle metastable nuclides in NNDC data and multiplicities in MT=5 data + +.. _26fb93: https://github.com/mit-crpg/openmc/commit/26fb93 +.. _2f07c0: https://github.com/mit-crpg/openmc/commit/2f07c0 +.. _e6abb9: https://github.com/mit-crpg/openmc/commit/e6abb9 +.. _291b45: https://github.com/mit-crpg/openmc/commit/291b45 + +------------ +Contributors +------------ + +This release contains new contributions from the following people: + +- `Will Boyd `_ +- `Matt Ellis `_ +- `Sterling Harper `_ +- `Bryan Herman `_ +- `Nicholas Horelik `_ +- `Anton Leontiev `_ +- `Adam Nelson `_ +- `Paul Romano `_ +- `Jon Walsh `_ +- `John Xia `_ diff --git a/docs/source/releasenotes/0.7.0.rst b/docs/source/releasenotes/0.7.0.rst new file mode 100644 index 000000000..e7b72686a --- /dev/null +++ b/docs/source/releasenotes/0.7.0.rst @@ -0,0 +1,65 @@ +============================== +Release Notes for OpenMC 0.7.0 +============================== + +------------------- +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). + +------------ +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 + +--------- +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 + +.. _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 + +------------ +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 `_ +- `Jon Walsh `_ diff --git a/docs/source/releasenotes/0.7.1.rst b/docs/source/releasenotes/0.7.1.rst new file mode 100644 index 000000000..f1ab0d1aa --- /dev/null +++ b/docs/source/releasenotes/0.7.1.rst @@ -0,0 +1,89 @@ +============================== +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 +------------------- + +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). + +------------ +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 + +--------- +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 + +.. _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 +------------ + +This release contains new contributions from the following people: + +- `Will Boyd `_ +- `Sterling Harper `_ +- `Bryan Herman `_ +- `Colin Josey `_ +- `Adam Nelson `_ +- `Paul Romano `_ +- `Kelly Rowland `_ +- `Sam Shaner `_ +- `Jon Walsh `_ diff --git a/docs/source/releasenotes/0.8.0.rst b/docs/source/releasenotes/0.8.0.rst new file mode 100644 index 000000000..52a03d614 --- /dev/null +++ b/docs/source/releasenotes/0.8.0.rst @@ -0,0 +1,94 @@ +============================== +Release Notes for OpenMC 0.8.0 +============================== + +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. + +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: + +- ``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 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 +------------ + +- 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 +--------- + +- 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 + +.. _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 +------------ + +This release contains new contributions from the following people: + +- `Will Boyd `_ +- `Derek Gaston `_ +- `Sterling Harper `_ +- `Colin Josey `_ +- `Jingang Liang `_ +- `Adam Nelson `_ +- `Paul Romano `_ +- `Kelly Rowland `_ +- `Sam Shaner `_ diff --git a/docs/source/releasenotes/0.9.0.rst b/docs/source/releasenotes/0.9.0.rst new file mode 100644 index 000000000..6a9961e69 --- /dev/null +++ b/docs/source/releasenotes/0.9.0.rst @@ -0,0 +1,150 @@ +============================== +Release Notes for OpenMC 0.9.0 +============================== + +.. currentmodule:: openmc + +This release of OpenMC is the first release to use a new native HDF5 cross +section format rather than ACE format cross sections. Other significant new +features include a nuclear data interface in the Python API (:mod:`openmc.data`) +a stochastic volume calculation capability, a random sphere packing algorithm +that can handle packing fractions up to 60%, and a new XML parser with +significantly better performance than the parser used previously. + +.. caution:: With the new cross section format, the default energy units are now + **electronvolts (eV)** rather than megaelectronvolts (MeV)! If you + are specifying an energy filter for a tally, make sure you use + units of eV now. + +The Python API continues to improve over time; several backwards incompatible +changes were made in the API which users of previous versions should take note +of: + +- Each type of tally filter is now specified with a separate class. For example:: + + energy_filter = openmc.EnergyFilter([0.0, 0.625, 4.0, 1.0e6, 20.0e6]) + +- Several attributes of the :class:`Plot` class have changed (``color`` -> + ``color_by`` and ``col_spec`` > ``colors``). :attr:`Plot.colors` now accepts a + dictionary mapping :class:`Cell` or :class:`Material` instances to RGB + 3-tuples or string colors names, e.g.:: + + plot.colors = { + fuel: 'yellow', + water: 'blue' + } + +- ``make_hexagon_region`` is now :func:`get_hexagonal_prism` +- Several changes in :class:`Settings` attributes: + + - ``weight`` is now set as ``Settings.cutoff['weight']`` + - Shannon entropy is now specified by passing a :class:`openmc.Mesh` to + :attr:`Settings.entropy_mesh` + - Uniform fission site method is now specified by passing a + :class:`openmc.Mesh` to :attr:`Settings.ufs_mesh` + - All ``sourcepoint_*`` options are now specified in a + :attr:`Settings.sourcepoint` dictionary + - Resonance scattering method is now specified as a dictionary in + :attr:`Settings.resonance_scattering` + - Multipole is now turned on by setting ``Settings.temperature['multipole'] = + True`` + - The ``output_path`` attribute is now ``Settings.output['path']`` + +- All the ``openmc.mgxs.Nu*`` classes are gone. Instead, a ``nu`` argument was + added to the constructor of the corresponding classes. + +------------------- +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 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 +------------ + +- Stochastic volume calculations +- Multi-delayed group cross section generation +- Ability to calculate multi-group cross sections over meshes +- Temperature interpolation on cross section data +- Nuclear data interface in Python API, :mod:`openmc.data` +- Allow cutoff energy via :attr:`Settings.cutoff` +- Ability to define fuel by enrichment (see :meth:`Material.add_element`) +- Random sphere packing for TRISO particle generation, + :func:`openmc.model.pack_trisos` +- Critical eigenvalue search, :func:`openmc.search_for_keff` +- Model container, :class:`openmc.model.Model` +- In-line plotting in Jupyter, :func:`openmc.plot_inline` +- Energy function tally filters, :class:`openmc.EnergyFunctionFilter` +- Replaced FoX XML parser with `pugixml `_ +- Cell/material instance counting, :meth:`Geometry.determine_paths` +- Differential tallies (see :class:`openmc.TallyDerivative`) +- Consistent multi-group scattering matrices +- Improved documentation and new Jupyter notebooks +- OpenMOC compatibility module, :mod:`openmc.openmoc_compatible` + +--------- +Bug Fixes +--------- + +- c5df6c_: Fix mesh filter max iterator check +- 1cfa39_: Reject external source only if 95% of sites are rejected +- 335359_: Fix bug in plotting meshlines +- 17c678_: Make sure system_clock uses high-resolution timer +- 23ec0b_: Fix use of S(a,b) with multipole data +- 7eefb7_: Fix several bugs in tally module +- 7880d4_: Allow plotting calculation with no boundary conditions +- ad2d9f_: Fix filter weight missing when scoring all nuclides +- 59fdca_: Fix use of source files for fixed source calculations +- 9eff5b_: Fix thermal scattering bugs +- 7848a9_: Fix combined k-eff estimator producing NaN +- f139ce_: Fix printing bug for tallies with AggregateNuclide +- b8ddfa_: Bugfix for short tracks near tally mesh edges +- ec3cfb_: Fix inconsistency in filter weights +- 5e9b06_: Fix XML representation for verbosity +- c39990_: Fix bug tallying reaction rates with multipole on +- c6b67e_: Fix fissionable source sampling bug +- 489540_: Check for void materials in tracklength tallies +- f0214f_: Fixes/improvements to the ARES algorithm + +.. _c5df6c: https://github.com/mit-crpg/openmc/commit/c5df6c +.. _1cfa39: https://github.com/mit-crpg/openmc/commit/1cfa39 +.. _335359: https://github.com/mit-crpg/openmc/commit/335359 +.. _17c678: https://github.com/mit-crpg/openmc/commit/17c678 +.. _23ec0b: https://github.com/mit-crpg/openmc/commit/23ec0b +.. _7eefb7: https://github.com/mit-crpg/openmc/commit/7eefb7 +.. _7880d4: https://github.com/mit-crpg/openmc/commit/7880d4 +.. _ad2d9f: https://github.com/mit-crpg/openmc/commit/ad2d9f +.. _59fdca: https://github.com/mit-crpg/openmc/commit/59fdca +.. _9eff5b: https://github.com/mit-crpg/openmc/commit/9eff5b +.. _7848a9: https://github.com/mit-crpg/openmc/commit/7848a9 +.. _f139ce: https://github.com/mit-crpg/openmc/commit/f139ce +.. _b8ddfa: https://github.com/mit-crpg/openmc/commit/b8ddfa +.. _ec3cfb: https://github.com/mit-crpg/openmc/commit/ec3cfb +.. _5e9b06: https://github.com/mit-crpg/openmc/commit/5e9b06 +.. _c39990: https://github.com/mit-crpg/openmc/commit/c39990 +.. _c6b67e: https://github.com/mit-crpg/openmc/commit/c6b67e +.. _489540: https://github.com/mit-crpg/openmc/commit/489540 +.. _f0214f: https://github.com/mit-crpg/openmc/commit/f0214f + +------------ +Contributors +------------ + +This release contains new contributions from the following people: + +- `Will Boyd `_ +- `Sterling Harper `_ +- `Qingming He <906459647@qq.com>`_ +- `Colin Josey `_ +- `Travis Labossiere-Hickman `_ +- `Jingang Liang `_ +- `Amanda Lund `_ +- `Adam Nelson `_ +- `Paul Romano `_ +- `Sam Shaner `_ +- `Jon Walsh `_ diff --git a/docs/source/releasenotes/index.rst b/docs/source/releasenotes/index.rst new file mode 100644 index 000000000..3c66b6a60 --- /dev/null +++ b/docs/source/releasenotes/index.rst @@ -0,0 +1,27 @@ +.. _releasenotes: + +============= +Release Notes +============= + +.. toctree:: + :maxdepth: 1 + + 0.10.0 + 0.9.0 + 0.8.0 + 0.7.1 + 0.7.0 + 0.6.2 + 0.6.1 + 0.6.0 + 0.5.4 + 0.5.3 + 0.5.2 + 0.5.1 + 0.5.0 + 0.4.4 + 0.4.3 + 0.4.2 + 0.4.1 + 0.4.0