What’s New in 0.13.1¶
This release of OpenMC includes many bug fixes as well as improvements in
geometry modeling, mesh functionality, source specification, depletion
capabilities, and other general enhancements. The depletion module features a
new transport operator,
openmc.deplete.IndependentOperator, that allows
a depletion calculation to be performed using arbitrary one-group cross sections
(e.g., generated by an external solver) along with a
openmc.deplete.MicroXS class for managing one-group cross sections. The
track file generation capability has been significantly overhauled and a new
openmc.Tracks class was introduced to allow access to information in
track files from the Python API. Support has been added for new ENDF thermal
scattering evaluations that use mixed coherent/incoherent elastic scattering.
Compatibility Notes and Deprecations¶
openmc.deplete.Operatorclass has been renamed
openmc.deplete.ResultsListclass has been renamed to
openmc.deplete.Resultsand no longer requires you to call the
from_hdf5()method in order to create it; instead, you can directly instantiate it.
A few methods that represent k-effective have been renamed for the sake of consistency:
openmc.stats.SphericalIndependentclass, which used to accept a distribution for
thetanow accepts a distribution for
cos_thetainstead in order to more easily handle the common case of specifying a uniform spatial distribution over a sphere (also see the new
If you are building OpenMC from source, note that several of our CMake options have been changed:
optimizeoptions have been removed; instead, use the standard CMAKE_BUILD_TYPE variable.
Materialclass has several new methods and attributes:
add_components()methods allows you to add multiple nuclides/elements to a material with a single call by passing a dictionary.
get_activity()method returns the activity of a material in Bq, Bq/g, or Bq/cm³.
remove_element()method removes an element from a material
get_nuclide_atoms()method gives the number of atoms of each nuclide in a material
All mesh classes now have a
volumesproperty that provides the volume of each mesh element as well as
Support for externally managed MOAB meshes or libMesh meshes.
Multiple discrete distributions can be merged with the new
Univariate distributions in the
openmc.statsmodule now have
openmc_sample_external_sourcefunction has been added to the C API with a corresponding Python binding
The track file generation capability has been completely overhauled. Track files now include much more information, and a new
Tracksclass allows access to track file information from the Python API and has a
write_to_vtk()method for writing a VTK file. Multiple tracks are now written to a single file (one per MPI rank).
openmc.EnergyFilter.from_group_structure()method provides a way of creating an energy filter with a group structure identified by name.
openmc.mgxs.ReducedAbsorptionXSclass produces a multigroup cross section representing “reduced” absorption (absorption less neutron production from (n,xn) reactions).
Added support in the Python API and HDF5 nuclear data format for new ENDF thermal neutron scattering evaluations with mixed coherent elastic and incoherent elastic.
CMake now relies on
find_package(MPI)for a more standard means of identifying an MPI compiler configuration.