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OpenMC 0.13.3
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@paulromano paulromano released this 29 Mar 19:22
· 530 commits to develop since this release
v0.13.3
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This release of OpenMC includes many bug fixes, performance improvements, and several notable new features. Some of the highlights include support for MCPL source files, NCrystal thermal scattering materials, and a new openmc.stats.MeshSpatial class that allows a source distribution to be specified over a mesh. Additionally, OpenMC now allows you to export your model as a single XML file rather than separate XML files for geometry, materials, settings, and tallies.

Compatability Notes and Deprecations

  • Atomic mass data used in openmc.data.atomic_mass has been updated to AME 2020, which results in slightly different masses.

New Features

  • Support was added for MCPL files to be used as external sources. Additionally, source points and surfaces sources can be written as MCPL files instead of HDF5 files. (#2116)
  • Support was added for NCrystal thermal scattering materials. (#2222)
  • The openmc.CylindricalMesh and openmc.SphericalMesh classes now have an origin attribute that changes the center of the mesh. (#2256)
  • A new openmc.model.Polygon class allows defining generalized 2D polygons. (#2266)
  • A new openmc.data.decay_energy function and openmc.Material.get_decay_heat method enable determination of decay heat from a single nuclide or material. (#2287)
  • Full models can now be written as a single XML file rather than separate geometry, materials, settings, and tallies XML files. (#2291)
  • Discrete distributions are now sampled using alias sampling, which is O(1) in time. (#2329)
  • The new openmc.stats.MeshSpatial allows a spatial source distribution to be specified with source strengths for each mesh element. (#2334)
  • The new openmc.Geometry.get_surfaces_by_name method returns a list of matching surfaces in a geometry. (#2347)
  • A new openmc.Settings.create_delayed_neutrons attribute controls whether delayed neutrons are created during a simulation. (#2348)
  • The openmc.deplete.Results.export_to_materials method now takes a path argument. (#2364)
  • A new openmc.EnergyFilter.get_tabular method allows one to create a tabular distribution based on tally results using an energy filter. (#2371)
  • Several methods in the openmc.Material class that require a volume to be set (e.g., openmc.Material.get_mass) now accept a volume argument. (#2412)

Bug Fixes

  • Fix for finding redundant surfaces (#2263)
  • Adds tolerance for temperatures slightly out of bounds (#2265)
  • Fix getter/setter for weight window bounds (#2275)
  • Make sure Chain.reduce preserves decay source (#2283)
  • Fix array shape for weight window bounds (#2284)
  • Fix for non-zero CDF start points in TSL data (#2290)
  • Fix a case where inelastic scattering yield is zero (#2295)
  • Prevent Compton profile out-of-bounds memory access (#2297)
  • Produce light particles from decay (#2301)
  • Fix zero runtime attributes in depletion statepoints (#2302)
  • Fix bug in openmc.Universe.get_nuclide_densities (#2310)
  • Only show print output from depletion on rank 0 (#2311)
  • Fix photon transport with no atomic relaxation data (#2312)
  • Fix for precedence in region expressions (#2318)
  • Allow source particles with energy below cutoff (#2319)
  • Fix IncidentNeutron.from_njoy for high temperatures (#2320)
  • Add capability to unset cell temperatures (#2323)
  • Fix in plot_xs when S(a,b) tables are present (#2335)
  • Various fixes for tally triggers (#2344)
  • Raise error when mesh is flat (#2363)
  • Don't call normalize inside Tabular.mean (#2375)
  • Avoid out-of-bounds access in inelastic scatter sampling (#2378)
  • Use correct direction for anisotropic fission (#2381)
  • Fix several thermal scattering nuclide assignments (#2382)
  • Fix _materials_by_id attribute in Model (#2385)
  • Updates to batch checks for simulation restarts (#2390)
  • write_data_to_vtk volume normalization correction (#2397)
  • Enable generation of JEFF 3.3 depletion chain (#2410)
  • Fix spherical to Cartesian coordinate conversion (#2417)
  • Handle zero photon cross sections in IncidentPhoton.from_ace (#2433)
  • Fix hybrid depletion when nuclides are not present (#2436)
  • Fix bug in cylindrical and spherical meshes (#2439)
  • Improvements to mesh radial boundary coincidence (#2443)

Contributors

Contributors

paulromano, gonuke, and 22 other contributors
Assets 3
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