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 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.Muir
class has been replaced by aopenmc.stats.muir
function that returns an instance ofopenmc.stats.Normal
.
- 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 a~openmc.RegularMesh.from_domain
classmethod. - The
openmc.CylindricalMesh
class now has a~openmc.CylindricalMesh.from_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 new~openmc.Material.decay_photon_energy
attribute that gives the decay photon energy spectrum from the material based on its constituent nuclides. - The
openmc.deplete.StepResult
now has a~openmc.deplete.StepResult.get_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).
- 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