.. currentmodule:: openmc
This release of OpenMC includes several bug fixes, performance improvements for complex geometries and depletion simulations, and other general enhancements. Notably, a capability has been added to compute the photon spectra from decay of unstable nuclides. Alongside that, a new :data:`openmc.config` configuration variable has been introduced that allows easier configuration of data sources. Additionally, users can now perform cell or material rejection when sampling external source distributions.
- If you are building against libMesh for unstructured mesh tally support, version 1.6 or higher is now required.
- The
openmc.stats.Muirclass has been replaced by a :func:`openmc.stats.muir` function that returns an instance of :class:`openmc.stats.Normal`.
- The :meth:`openmc.Material.get_nuclide_atom_densities` method now takes an
optional
nuclideargument. - Functions/methods in the :mod:`openmc.deplete` module now accept times in
Julian years (
'a'). - The :meth:`openmc.Universe.plot` method now allows a pre-existing axes object to be passed in.
- Performance optimization for geometries with many complex regions.
- Performance optimization for depletion by avoiding deepcopies and caching reaction rates.
- The :class:`openmc.RegularMesh` class now has a :meth:`~openmc.RegularMesh.from_domain` classmethod.
- The :class:`openmc.CylindricalMesh` class now has a :meth:`~openmc.CylindricalMesh.from_domain` classmethod.
- Improved method to condense diffusion coefficients from the :mod:`openmc.mgxs` module.
- A new :data:`openmc.config` configuration variable has been introduced that allows data sources to be specified at runtime or via environment variables.
- The :class:`openmc.EnergyFunctionFilter` class now supports multiple interpolation schemes, not just linear-linear interpolation.
- The :class:`openmc.DAGMCUniverse` class now has
material_names,n_cells, andn_surfacesattributes. - A new :func:`openmc.data.decay_photon_energy` function has been added that returns the energy spectrum of photons emitted from the decay of an unstable nuclide.
- The :class:`openmc.Material` class also has a new :attr:`~openmc.Material.decay_photon_energy` attribute that gives the decay photon energy spectrum from the material based on its constituent nuclides.
- The :class:`openmc.deplete.StepResult` now has a :meth:`~openmc.deplete.StepResult.get_material` method.
- The :class:`openmc.Source` class now takes a
domainsargument that specifies a list of cells, materials, or universes that is used to reject source sites (i.e., if the sampled sites are not within the specified domain, they are rejected).
- Delay call to Tally::set_strides
- Fix reading reference direction from XML for angular distributions
- Fix erroneous behavior in Material.add_components
- Fix reading thermal elastic data from ACE
- Fix reading source file with time attribute
- Fix conversion of multiple thermal scattering data files from ACE
- Fix reading values from wwinp file
- Handle possibility of .ppm file in Universe.plot
- Update volume calc types to mitigate overflow issues