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Paul Romano 2019-05-29 07:06:10 -05:00
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docs/source/index.rst
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@ -35,7 +35,7 @@ list <https://groups.google.com/forum/?fromgroups=#!forum/openmc-users>`_.
quickinstall
examples/index
releasenotes
releasenotes/index
methods/index
usersguide/index
devguide/index

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.. _releasenotes:
===============================
Release Notes for OpenMC 0.10.0
===============================

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.. _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.

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.. _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

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.. _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 <trace> 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 <density> 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

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.. _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 <estimator> 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

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.. _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 <no_reduce>.
- Real-time XML validation in GNU Emacs with RELAX NG schemata.
- Writing state points every n batches with <state_point interval="..." />
- Suppress creation of summary.out and cross_sections.out by default with option
to turn them on with <output> 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 <upper_right> 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

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.. _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 <criticality> element is deprecated and was replaced with <eigenvalue>.
- 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

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.. _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 <element> rather than
<nuclide>.
- 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

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.. _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 <element>
- 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

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.. _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

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.. _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 <smharper@mit.edu>`_
- `Bryan Herman <bherman@mit.edu>`_
- `Nick Horelik <nhorelik@mit.edu>`_
- `Adam Nelson <nelsonag@umich.edu>`_
- `Paul Romano <paul.k.romano@gmail.com>`_
- `Tuomas Viitanen <tuomas.viitanen@vtt.fi>`_
- `Jon Walsh <walshjon@mit.edu>`_

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.. _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 <natural_elements> 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 <element> 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 <smharper@mit.edu>`_
- `Bryan Herman <bherman@mit.edu>`_
- `Nick Horelik <nhorelik@mit.edu>`_
- `Adam Nelson <nelsonag@umich.edu>`_
- `Paul Romano <paul.k.romano@gmail.com>`_
- `Jon Walsh <walshjon@mit.edu>`_

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.. _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 <smharper@mit.edu>`_
- `Bryan Herman <bherman@mit.edu>`_
- `Adam Nelson <nelsonag@umich.edu>`_
- `Paul Romano <paul.k.romano@gmail.com>`_
- `Jon Walsh <walshjon@mit.edu>`_
- `Will Boyd <wbinventor@gmail.com>`_

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.. _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 <wbinventor@gmail.com>`_
- `Matt Ellis <mellis13@mit.edu>`_
- `Sterling Harper <smharper@mit.edu>`_
- `Bryan Herman <bherman@mit.edu>`_
- `Nicholas Horelik <nicholas.horelik@gmail.com>`_
- `Anton Leontiev <bunder@t-25.ru>`_
- `Adam Nelson <nelsonag@umich.edu>`_
- `Paul Romano <paul.k.romano@gmail.com>`_
- `Jon Walsh <walshjon@mit.edu>`_
- `John Xia <john.danger.xia@gmail.com>`_

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==============================
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 <wbinventor@gmail.com>`_
- `Matt Ellis <mellis13@mit.edu>`_
- `Sterling Harper <sterlingmharper@mit.edu>`_
- `Bryan Herman <bherman@mit.edu>`_
- `Nicholas Horelik <nicholas.horelik@gmail.com>`_
- `Colin Josey <cjosey@mit.edu>`_
- `William Lyu <PaleNeutron@users.noreply.github.com>`_
- `Adam Nelson <nelsonag@umich.edu>`_
- `Paul Romano <paul.k.romano@gmail.com>`_
- `Anthony Scopatz <scopatz@gmail.com>`_
- `Jon Walsh <walshjon@mit.edu>`_

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==============================
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 <wbinventor@gmail.com>`_
- `Sterling Harper <sterlingmharper@mit.edu>`_
- `Bryan Herman <hermab53@gmail.com>`_
- `Colin Josey <cjosey@mit.edu>`_
- `Adam Nelson <nelsonag@umich.edu>`_
- `Paul Romano <paul.k.romano@gmail.com>`_
- `Kelly Rowland <kellylynnerowland@gmail.com>`_
- `Sam Shaner <samuelshaner@gmail.com>`_
- `Jon Walsh <walshjon@mit.edu>`_

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==============================
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 <wbinventor@gmail.com>`_
- `Derek Gaston <friedmud@gmail.com>`_
- `Sterling Harper <sterlingmharper@gmail.com>`_
- `Colin Josey <cjosey@mit.edu>`_
- `Jingang Liang <liangjg2008@gmail.com>`_
- `Adam Nelson <nelsonag@umich.edu>`_
- `Paul Romano <paul.k.romano@gmail.com>`_
- `Kelly Rowland <kellylynnerowland@gmail.com>`_
- `Sam Shaner <samuelshaner@gmail.com>`_

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==============================
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 <http://pugixml.org/>`_
- 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 <wbinventor@gmail.com>`_
- `Sterling Harper <sterlingmharper@gmail.com>`_
- `Qingming He <906459647@qq.com>`_
- `Colin Josey <cjosey@mit.edu>`_
- `Travis Labossiere-Hickman <tjlaboss@mit.edu>`_
- `Jingang Liang <liangjg2008@gmail.com>`_
- `Amanda Lund <alund@anl.gov>`_
- `Adam Nelson <nelsonag@umich.edu>`_
- `Paul Romano <paul.k.romano@gmail.com>`_
- `Sam Shaner <samuelshaner@gmail.com>`_
- `Jon Walsh <jonathan.a.walsh@gmail.com>`_

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.. _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