==================== What's New in 0.13.3 ==================== .. currentmodule:: openmc ------- Summary ------- 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 :class:`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. ------------------------------------ Compatibility Notes and Deprecations ------------------------------------ - Atomic mass data used in :func:`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 :class:`~openmc.CylindricalMesh` and :class:`~openmc.SphericalMesh` classes now have an ``origin`` attribute that changes the center of the mesh. (`#2256 `_) - A new :class:`openmc.model.Polygon` class allows defining generalized 2D polygons. (`#2266 `_) - A new :func:`openmc.data.decay_energy` function and :meth:`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 :class:`openmc.stats.MeshSpatial` allows a spatial source distribution to be specified with source strengths for each mesh element. (`#2334 `_) - The new :meth:`openmc.Geometry.get_surfaces_by_name` method returns a list of matching surfaces in a geometry. (`#2347 `_) - A new :attr:`openmc.Settings.create_delayed_neutrons` attribute controls whether delayed neutrons are created during a simulation. (`#2348 `_) - The :meth:`openmc.deplete.Results.export_to_materials` method now takes a ``path`` argument. (`#2364 `_) - A new :meth:`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 :class:`openmc.Material` class that require a volume to be set (e.g., :meth:`~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 ------------ - `Hunter Belanger `_ - `Rémi Delaporte-Mathurin `_ - `Christopher Fichtlscherer `_ - `Valerio Giusti `_ - `Chris Keckler `_ - `Kalin Kiesling `_ - `Thomas Kittelmann `_ - `Erik Knudsen `_ - `Colin Larmier `_ - `Amanda Lund `_ - `Jose Ignacio Marquez Damien `_ - `Josh May `_ - `Patrick Myers `_ - `Baptiste Mouginot `_ - `April Novak `_ - `Matthew Nyberg `_ - `Ethan Peterson `_ - `Gavin Ridley `_ - `Paul Romano `_ - `Patrick Shriwise `_ - `Jonathan Shimwell `_ - `Paul Wilson `_ - `Olek Yardas `_ - `Jiankai Yu `_