What’s New in 0.13.2¶
Summary¶
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 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.
Compatibility Notes and Deprecations¶
If you are building against libMesh for unstructured mesh tally support, version 1.6 or higher is now required.
The
openmc.stats.Muir
class has been replaced by aopenmc.stats.muir()
function that returns an instance ofopenmc.stats.Normal
.
New Features¶
The
openmc.Material.get_nuclide_atom_densities()
method now takes an optionalnuclide
argument.Functions/methods in the
openmc.deplete
module now accept times in Julian years ('a'
).The
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
openmc.RegularMesh
class now has afrom_domain()
classmethod.The
openmc.CylindricalMesh
class now has afrom_domain()
classmethod.Improved method to condense diffusion coefficients from the
openmc.mgxs
module.A new
openmc.config
configuration variable has been introduced that allows data sources to be specified at runtime or via environment variables.The
openmc.EnergyFunctionFilter
class now supports multiple interpolation schemes, not just linear-linear interpolation.The
openmc.DAGMCUniverse
class now hasmaterial_names
,n_cells
, andn_surfaces
attributes.A new
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
openmc.Material
class also has a newdecay_photon_energy
attribute that gives the decay photon energy spectrum from the material based on its constituent nuclides.The
openmc.deplete.StepResult
now has aget_material()
method.The
openmc.Source
class now takes adomains
argument 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).