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Release of version 0.15.0 (#3050)
This commit is contained in:
Paul Romano
GitHub
parent
00faa7d698
commit
55b52b7ef3
60 changed files with 464 additions and 85 deletions
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@ -3,8 +3,8 @@ project(openmc C CXX)
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# Set version numbers
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set(OPENMC_VERSION_MAJOR 0)
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set(OPENMC_VERSION_MINOR 14)
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set(OPENMC_VERSION_RELEASE 1)
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set(OPENMC_VERSION_MINOR 15)
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set(OPENMC_VERSION_RELEASE 0)
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set(OPENMC_VERSION ${OPENMC_VERSION_MAJOR}.${OPENMC_VERSION_MINOR}.${OPENMC_VERSION_RELEASE})
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configure_file(include/openmc/version.h.in "${CMAKE_BINARY_DIR}/include/openmc/version.h" @ONLY)
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@ -69,9 +69,9 @@ copyright = '2011-2024, Massachusetts Institute of Technology, UChicago Argonne
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# built documents.
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#
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# The short X.Y version.
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version = "0.14"
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version = "0.15"
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# The full version, including alpha/beta/rc tags.
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release = "0.14.1-dev"
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release = "0.15.0"
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# The language for content autogenerated by Sphinx. Refer to documentation
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# for a list of supported languages.
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@ -284,9 +284,9 @@ then, OpenMC will only use up to the :math:`P_1` data.
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.. note:: This element is not used in the continuous-energy
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:ref:`energy_mode`.
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------------------------
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--------------------------------
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``<max_history_splits>`` Element
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------------------------
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--------------------------------
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The ``<max_history_splits>`` element indicates the number of times a particle can split during a history.
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@ -100,11 +100,11 @@ terms on the right hand side.
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.. math::
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:label: transport
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\begin{align*}
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\begin{aligned}
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\mathbf{\Omega} \cdot \mathbf{\nabla} \psi(\mathbf{r},\mathbf{\Omega},E) & + \Sigma_t(\mathbf{r},E) \psi(\mathbf{r},\mathbf{\Omega},E) = \\
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& \int_0^\infty d E^\prime \int_{4\pi} d \Omega^{\prime} \Sigma_s(\mathbf{r},\mathbf{\Omega}^\prime \rightarrow \mathbf{\Omega}, E^\prime \rightarrow E) \psi(\mathbf{r},\mathbf{\Omega}^\prime, E^\prime) \\
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& + \frac{\chi(\mathbf{r}, E)}{4\pi k_{eff}} \int_0^\infty dE^\prime \nu \Sigma_f(\mathbf{r},E^\prime) \int_{4\pi}d \Omega^\prime \psi(\mathbf{r},\mathbf{\Omega}^\prime,E^\prime)
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\end{align*}
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\end{aligned}
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In Equation :eq:`transport`, :math:`\psi` is the angular neutron flux. This
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parameter represents the total distance traveled by all neutrons in a particular
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262
docs/source/releasenotes/0.15.0.rst
Normal file
262
docs/source/releasenotes/0.15.0.rst
Normal file
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@ -0,0 +1,262 @@
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====================
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What's New in 0.15.0
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====================
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.. currentmodule:: openmc
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-------
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Summary
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-------
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This release of OpenMC includes many bug fixes, performance improvements, and
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several notable new features. The major highlight of this release is the
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introduction of a new transport solver based on the random ray method, which is
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fully described in the :ref:`user's guide <random_ray>`. Other notable additions
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include a mesh-based source class (:class:`openmc.MeshSource`), a generalization
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of source domain rejection through the notion of "constraints", and new methods
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on mesh-based classes for computing material volume fractions and homogenized
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materials.
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------------------------------------
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Compatibility Notes and Deprecations
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------------------------------------
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Previously, specifying domain rejection for a source was only possible on the
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:class:`~openmc.IndependentSoure` class and worked by specifying a `domains`
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argument. This capability has been generalized to all source classes and
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expanded as well; specifying a domain to reject on should now be done with the
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`constraints` argument as follows::
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source = openmc.IndependentSource(..., constraints={'domains': [cell]})
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The `domains` argument is deprecated and will be removed in a future version of
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OpenMC. Similarly, the ``only_fissionable`` argument to
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:class:`openmc.stats.Box` has been replaced by a `'fissionable'` constraint.
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That is, instead of specifying::
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space = openmc.stats.Box(lower_left, upper_right, only_fissionable=True)
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source = openmc.IndependentSource(space=space)
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You should now provide the constraint as::
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space = openmc.stats.Box(lower_left, upper_right)
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source = openmc.IndependentSource(space=space, constraints={'fissionable': True})
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The :attr:`openmc.Settings.max_splits` attribute was renamed to
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``max_history_splits`` and its default value has been changed to 1e7 (`#2954
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<https://github.com/openmc-dev/openmc/pull/2954>`_).
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------------
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New Features
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------------
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- When running OpenMC in volume calculation mode, only atomic weight ratio data
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is loaded from data files which reduces initialization time. (`#2741
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<https://github.com/openmc-dev/openmc/pull/2741>`_)
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- Introduced a ``GeometryState`` class in C++ to better separate particle and
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geometry data. (`#2744 <https://github.com/openmc-dev/openmc/pull/2744>`_))
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- A new :class:`openmc.MaterialFromFilter` class allows filtering tallies by
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which material a particle came from. (`#2750
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<https://github.com/openmc-dev/openmc/pull/2750>`_)
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- Implemented a :meth:`openmc.deplete.MicroXS.from_multigroup_flux` method that
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generates microscopic cross sections for depletion from a predetermined
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multigroup flux. (`#2755 <https://github.com/openmc-dev/openmc/pull/2755>`_)
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- A new :class:`openmc.MeshSource` class enables the specification of a source
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distribution over a mesh, where each mesh element has a different
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energy/angle/time distribution. (`#2759
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<https://github.com/openmc-dev/openmc/pull/2759>`_)
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- Improve performance of depletion solver by utilizing CSR sparse matrix
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representation. (`#2764 <https://github.com/openmc-dev/openmc/pull/2764>`_,
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`#2771 <https://github.com/openmc-dev/openmc/pull/2771>`_)
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- Added a :meth:`openmc.CylindricalMesh.get_indices_at_coords` method that
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provides the mesh element index corresponding to a given point in space.
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(`#2782 <https://github.com/openmc-dev/openmc/pull/2782>`_)
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- Added a `path` argument to the :meth:`openmc.deplete.Integrator.integrate`
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method. (`#2784 <https://github.com/openmc-dev/openmc/pull/2784>`_)
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- Added a :meth:`openmc.Geometry.get_all_nuclides` method. (`#2796
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<https://github.com/openmc-dev/openmc/pull/2796>`_)
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- A new capability to compute material volume fractions over mesh elements was
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added in the :meth:`openmc.lib.Mesh.material_volumes` method. (`#2802
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<https://github.com/openmc-dev/openmc/pull/2802>`_)
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- A new transport solver was added based on the `random ray
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<https://doi.org/10.1016/j.jcp.2017.04.038>`_ method. (`#2823
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<https://github.com/openmc-dev/openmc/pull/2823>`_, `#2988
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<https://github.com/openmc-dev/openmc/pull/2988>`_)
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- Added a :attr:`openmc.lib.Material.depletable` attribute. (`#2843
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<https://github.com/openmc-dev/openmc/pull/2843>`_)
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- Added a :meth:`openmc.lib.Mesh.get_plot_bins` method and corresponding
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``openmc_mesh_get_plot_bins`` C API function that can be utilized to generate
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mesh tally visualizations in the plotter application. (`#2854
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<https://github.com/openmc-dev/openmc/pull/2854>`_)
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- Introduced a :func:`openmc.read_source_file` function that enables reading a
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source file from the Python API. (`#2858
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<https://github.com/openmc-dev/openmc/pull/2858>`_)
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- Added a ``bounding_box`` property on the :class:`openmc.RectilinearMesh` and
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:class:`openmc.UnstructuredMesh` classes. (`#2861
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<https://github.com/openmc-dev/openmc/pull/2861>`_)
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- Added a ``openmc_mesh_get_volumes`` C API function. (`#2869
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<https://github.com/openmc-dev/openmc/pull/2869>`_)
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- The :attr:`openmc.Settings.surf_source_write` dictionary now accepts `cell`,
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`cellfrom`, or `cellto` keys that limit surface source sites to those entering
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or leaving specific cells. (`#2888
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<https://github.com/openmc-dev/openmc/pull/2888>`_)
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- Added a :meth:`openmc.Region.plot` method that allows regions to be plotted
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directly. (`#2895 <https://github.com/openmc-dev/openmc/pull/2895>`_)
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- Implemented "contains" operator for the :class:`openmc.BoundingBox` class.
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(`#2906 <https://github.com/openmc-dev/openmc/pull/2906>`_)
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- Generalized source rejection via a new ``constraints`` argument to all source
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classes. (`#2916 <https://github.com/openmc-dev/openmc/pull/2916>`_)
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- Added a new :class:`openmc.MeshBornFilter` class that filters tally events
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based on which mesh element a particle was born in. (`#2925
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<https://github.com/openmc-dev/openmc/pull/2925>`_)
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- The :class:`openmc.Trigger` class now has a ``ignore_zeros`` argument that
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results in any bins with zero score to be ignored when checking the trigger.
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(`#2928 <https://github.com/openmc-dev/openmc/pull/2928>`_)
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- Introduced a :attr:`openmc.Settings.max_events` attribute that controls the
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maximum number of events a particle can undergo. (`#2945
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<https://github.com/openmc-dev/openmc/pull/2945>`_)
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- Added support for :class:`openmc.UnstructuredMesh` in the
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:class:`openmc.MeshSource` class. (`#2949
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<https://github.com/openmc-dev/openmc/pull/2949>`_)
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- Added a :meth:`openmc.MeshBase.get_homogenized_materials` method that computes
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homogenized materials over mesh elements. (`#2971
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<https://github.com/openmc-dev/openmc/pull/2971>`_)
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- Add an ``options`` argument to :class:`openmc.UnstructuredMesh` that allows
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configuring underlying data structures in MOAB. (`#2976
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<https://github.com/openmc-dev/openmc/pull/2976>`_)
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- Type hints were added to several classes in the :mod:`openmc.deplete` module.
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(`#2866 <https://github.com/openmc-dev/openmc/pull/2866>`_)
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---------
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Bug Fixes
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---------
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- Fix unit conversion in openmc.deplete.Results.get_mass (`#2761 <https://github.com/openmc-dev/openmc/pull/2761>`_)
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- Fix Lagrangian interpolation (`#2775 <https://github.com/openmc-dev/openmc/pull/2775>`_)
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- Depletion restart with MPI (`#2778 <https://github.com/openmc-dev/openmc/pull/2778>`_)
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- Modify depletion transfer rates test to be more robust (`#2779 <https://github.com/openmc-dev/openmc/pull/2779>`_)
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- Call simulation_finalize if needed when finalizing OpenMC (`#2790 <https://github.com/openmc-dev/openmc/pull/2790>`_)
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- F90_NONE Removal (MGMC tallying optimization) (`#2785 <https://github.com/openmc-dev/openmc/pull/2785>`_)
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- Correctly apply volumes to materials when using DAGMC geometries (`#2787 <https://github.com/openmc-dev/openmc/pull/2787>`_)
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- Add inline to openmc::interpolate (`#2789 <https://github.com/openmc-dev/openmc/pull/2789>`_)
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- Use huge_tree=True in lxml parsing (`#2791 <https://github.com/openmc-dev/openmc/pull/2791>`_)
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- OpenMPMutex "Copying" (`#2794 <https://github.com/openmc-dev/openmc/pull/2794>`_)
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- Do not link against several transitive dependencies of HDF5 (`#2797 <https://github.com/openmc-dev/openmc/pull/2797>`_)
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- Added check to length of input arguments for IndependantOperator (`#2799 <https://github.com/openmc-dev/openmc/pull/2799>`_)
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- Pytest Update Documentation (`#2801 <https://github.com/openmc-dev/openmc/pull/2801>`_)
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- Move 'import lxml' to third-party block of imports (`#2803 <https://github.com/openmc-dev/openmc/pull/2803>`_)
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- Fix creation of meshes when from loading settings from XML (`#2805 <https://github.com/openmc-dev/openmc/pull/2805>`_)
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- Avoid high memory use when writing unstructured mesh VTK files (`#2806 <https://github.com/openmc-dev/openmc/pull/2806>`_)
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- Consolidating thread information into the openmp interface header (`#2809 <https://github.com/openmc-dev/openmc/pull/2809>`_)
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- Prevent underflow in calculation of speed (`#2811 <https://github.com/openmc-dev/openmc/pull/2811>`_)
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- Provide error message if a cell path can't be determined (`#2812 <https://github.com/openmc-dev/openmc/pull/2812>`_)
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- Fix distribcell labels for lattices used as fill in multiple cells (`#2813 <https://github.com/openmc-dev/openmc/pull/2813>`_)
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- Make creation of spatial trees based on usage for unstructured mesh. (`#2815 <https://github.com/openmc-dev/openmc/pull/2815>`_)
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- Ensure particle direction is normalized for plotting / volume calculations (`#2816 <https://github.com/openmc-dev/openmc/pull/2816>`_)
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- Added missing meshes to documentation (`#2820 <https://github.com/openmc-dev/openmc/pull/2820>`_)
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- Reset timers at correct place in deplete (`#2821 <https://github.com/openmc-dev/openmc/pull/2821>`_)
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- Fix config change not propagating through to decay energies (`#2825 <https://github.com/openmc-dev/openmc/pull/2825>`_)
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- Ensure that implicit complement cells appear last in DAGMC universes (`#2838 <https://github.com/openmc-dev/openmc/pull/2838>`_)
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- Export model.tallies to XML in CoupledOperator (`#2840 <https://github.com/openmc-dev/openmc/pull/2840>`_)
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- Fix locating h5m files references in DAGMC universes (`#2842 <https://github.com/openmc-dev/openmc/pull/2842>`_)
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- Prepare for NumPy 2.0 (`#2845 <https://github.com/openmc-dev/openmc/pull/2845>`_)
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- Added missing functions and classes to openmc.lib docs (`#2847 <https://github.com/openmc-dev/openmc/pull/2847>`_)
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- Fix compilation on CentOS 7 (missing link to libdl) (`#2849 <https://github.com/openmc-dev/openmc/pull/2849>`_)
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- Adding resulting nuclide to cross section plot legend (`#2851 <https://github.com/openmc-dev/openmc/pull/2851>`_)
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- Updating file extension for Excel files when exporting MGXS data (`#2852 <https://github.com/openmc-dev/openmc/pull/2852>`_)
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- Removed error raising when calling warn (`#2853 <https://github.com/openmc-dev/openmc/pull/2853>`_)
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- Setting ``surf_source_`` attribute for DAGMC surfaces. (`#2857 <https://github.com/openmc-dev/openmc/pull/2857>`_)
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- Changing y axis label for heating plots (`#2859 <https://github.com/openmc-dev/openmc/pull/2859>`_)
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- Removed unused step_index arg from restart (`#2867 <https://github.com/openmc-dev/openmc/pull/2867>`_)
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- Fix issue with Cell::get_contained_cells() utility function (`#2873 <https://github.com/openmc-dev/openmc/pull/2873>`_)
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- Adding energy axis units to plot xs (`#2876 <https://github.com/openmc-dev/openmc/pull/2876>`_)
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- Set OpenMCOperator materials when diff_burnable_mats = True (`#2877 <https://github.com/openmc-dev/openmc/pull/2877>`_)
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- Fix expansion filter merging (`#2882 <https://github.com/openmc-dev/openmc/pull/2882>`_)
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- Added checks that tolerance value is between 0 and 1 (`#2884 <https://github.com/openmc-dev/openmc/pull/2884>`_)
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- Statepoint file loading refactor and CAPI function (`#2886 <https://github.com/openmc-dev/openmc/pull/2886>`_)
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- Added check for length of value passed into EnergyFilter (`#2887 <https://github.com/openmc-dev/openmc/pull/2887>`_)
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- Ensure that Model.run() works when specifying a custom XML path (`#2889 <https://github.com/openmc-dev/openmc/pull/2889>`_)
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- Updating docker file base to bookworm (`#2890 <https://github.com/openmc-dev/openmc/pull/2890>`_)
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- Clarifying documentation for cones (`#2892 <https://github.com/openmc-dev/openmc/pull/2892>`_)
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- Abort on cmake config if openmp requested but not found (`#2893 <https://github.com/openmc-dev/openmc/pull/2893>`_)
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- Tiny updates from experience building on Mac (`#2894 <https://github.com/openmc-dev/openmc/pull/2894>`_)
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- Added damage-energy as optional reaction for micro (`#2903 <https://github.com/openmc-dev/openmc/pull/2903>`_)
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- docs: add missing max_splits in settings specification (`#2910 <https://github.com/openmc-dev/openmc/pull/2910>`_)
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- Changed CI to use latest actions to get away from the Node 16 deprecation. (`#2912 <https://github.com/openmc-dev/openmc/pull/2912>`_)
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- Mkdir to always allow parents and exist ok (`#2914 <https://github.com/openmc-dev/openmc/pull/2914>`_)
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- Fixed small sphinx typo (`#2915 <https://github.com/openmc-dev/openmc/pull/2915>`_)
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- Hexagonal lattice iterators (`#2921 <https://github.com/openmc-dev/openmc/pull/2921>`_)
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- Fix Chain.form_matrix to work with scipy 1.12 (`#2922 <https://github.com/openmc-dev/openmc/pull/2922>`_)
|
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- Allow get_microxs_and_flux to use OPENMC_CHAIN_FILE environment variable (`#2934 <https://github.com/openmc-dev/openmc/pull/2934>`_)
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- Polygon fix to better handle colinear points (`#2935 <https://github.com/openmc-dev/openmc/pull/2935>`_)
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- Fix CMFD to work with scipy 1.13 (`#2936 <https://github.com/openmc-dev/openmc/pull/2936>`_)
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- Print warning if no natural isotopes when using add_element (`#2938 <https://github.com/openmc-dev/openmc/pull/2938>`_)
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- Update xtl and xtensor submodules (`#2941 <https://github.com/openmc-dev/openmc/pull/2941>`_)
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- Ensure two surfaces with different boundary type are not considered redundant (`#2942 <https://github.com/openmc-dev/openmc/pull/2942>`_)
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- Updated package versions in Dockerfile (`#2946 <https://github.com/openmc-dev/openmc/pull/2946>`_)
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- Add MPI calls to DAGMC external test (`#2948 <https://github.com/openmc-dev/openmc/pull/2948>`_)
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- Eliminate deprecation warnings from scipy and pandas (`#2951 <https://github.com/openmc-dev/openmc/pull/2951>`_)
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- Update math function unit test with catch2 (`#2955 <https://github.com/openmc-dev/openmc/pull/2955>`_)
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- Support track file writing for particle restart runs. (`#2957 <https://github.com/openmc-dev/openmc/pull/2957>`_)
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- Make UWUW optional (`#2965 <https://github.com/openmc-dev/openmc/pull/2965>`_)
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- Allow pure decay IndependentOperator (`#2966 <https://github.com/openmc-dev/openmc/pull/2966>`_)
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- Added fix to cfloat_endf for length 11 endf floats (`#2967 <https://github.com/openmc-dev/openmc/pull/2967>`_)
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- Moved apt get to optional CI parts (`#2970 <https://github.com/openmc-dev/openmc/pull/2970>`_)
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- Update bounding_box docstrings (`#2972 <https://github.com/openmc-dev/openmc/pull/2972>`_)
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- Added extra error checking on spherical mesh creation (`#2973 <https://github.com/openmc-dev/openmc/pull/2973>`_)
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- Update CODEOWNERS file (`#2974 <https://github.com/openmc-dev/openmc/pull/2974>`_)
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- Added error checking on cylindrical mesh (`#2977 <https://github.com/openmc-dev/openmc/pull/2977>`_)
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- Correction for histogram interpolation of Tabular distributions (`#2981 <https://github.com/openmc-dev/openmc/pull/2981>`_)
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- Enforce lower_left in lattice geometry (`#2982 <https://github.com/openmc-dev/openmc/pull/2982>`_)
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- Update random_dist.h comment to be less specific (`#2991 <https://github.com/openmc-dev/openmc/pull/2991>`_)
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- Apply memoization in get_all_universes (`#2995 <https://github.com/openmc-dev/openmc/pull/2995>`_)
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- Make sure skewed dataset is cast to bool properly (`#3001 <https://github.com/openmc-dev/openmc/pull/3001>`_)
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- Hexagonal lattice roundtrip (`#3003 <https://github.com/openmc-dev/openmc/pull/3003>`_)
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- Fix CylinderSector and IsogonalOctagon translations (`#3018 <https://github.com/openmc-dev/openmc/pull/3018>`_)
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- Sets used instead of lists when membership testing (`#3021 <https://github.com/openmc-dev/openmc/pull/3021>`_)
|
||||
- Fixing plot xs for when plotting element string reaction (`#3029 <https://github.com/openmc-dev/openmc/pull/3029>`_)
|
||||
- Fix shannon entropy broken link (`#3034 <https://github.com/openmc-dev/openmc/pull/3034>`_)
|
||||
- Only add png or h5 extension if not present in plots.py (`#3036 <https://github.com/openmc-dev/openmc/pull/3036>`_)
|
||||
- Fix non-existent path causing segmentation fault when saving plot (`#3038 <https://github.com/openmc-dev/openmc/pull/3038>`_)
|
||||
- Resolve warnings related to numpy 2.0 (`#3044 <https://github.com/openmc-dev/openmc/pull/3044>`_)
|
||||
- Update IsogonalOctagon to use xz basis (`#3045 <https://github.com/openmc-dev/openmc/pull/3045>`_)
|
||||
- Determine whether nuclides are fissionable in volume calc mode (`#3047 <https://github.com/openmc-dev/openmc/pull/3047>`_)
|
||||
- Avoiding more numpy 2.0 deprecation warnings (`#3049 <https://github.com/openmc-dev/openmc/pull/3049>`_)
|
||||
- Set DAGMC cell instances on surface crossing (`#3052 <https://github.com/openmc-dev/openmc/pull/3052>`_)
|
||||
|
||||
------------
|
||||
Contributors
|
||||
------------
|
||||
|
||||
- `Aidan Crilly <https://github.com/aidancrilly>`_
|
||||
- `April Novak <https://github.com/aprilnovak>`_
|
||||
- `Davide Mancusi <https://github.com/arekfu>`_
|
||||
- `Baptiste Mouginot <https://github.com/bam241>`_
|
||||
- `Chris Wagner <https://github.com/chrwagne>`_
|
||||
- `Lorenzo Chierici <https://github.com/church89>`_
|
||||
- `Catherine Yu <https://github.com/cxtherineyu>`_
|
||||
- `Erik Knudsen <https://github.com/ebknudsen>`_
|
||||
- `Ethan Peterson <https://github.com/eepeterson>`_
|
||||
- `Gavin Ridley <https://github.com/gridley>`_
|
||||
- `hsameer481 <https://github.com/hsameer481>`_
|
||||
- `Hunter Belanger <https://github.com/HunterBelanger>`_
|
||||
- `Isaac Meyer <https://github.com/icmeyer>`_
|
||||
- `Jin Whan Bae <https://github.com/jbae11>`_
|
||||
- `Joffrey Dorville <https://github.com/JoffreyDorville>`_
|
||||
- `John Tramm <https://github.com/jtramm>`_
|
||||
- `Yue Jin <https://github.com/kingyue737>`_
|
||||
- `Sigfrid Stjärnholm <https://github.com/Kladdy>`_
|
||||
- `Kimberly Meagher <https://github.com/kmeag>`_
|
||||
- `lhchg <https://github.com/lhchg>`_
|
||||
- `Luke Labrie-Cleary <https://github.com/LukeLabrie>`_
|
||||
- `Micah Gale <https://github.com/MicahGale>`_
|
||||
- `Nicholas Linden <https://github.com/nplinden>`_
|
||||
- `pitkajuh <https://github.com/pitkajuh>`_
|
||||
- `Rosie Barker <https://github.com/rlbarker>`_
|
||||
- `Paul Romano <https://github.com/paulromano>`_
|
||||
- `Patrick Shriwise <https://github.com/pshriwise>`_
|
||||
- `Jonathan Shimwell <https://github.com/Shimwell>`_
|
||||
- `Travis Labossiere-Hickman <https://github.com/tjlaboss>`_
|
||||
- `Vanessa Lulla <https://github.com/vanessalulla>`_
|
||||
- `Olek Yardas <https://github.com/yardasol>`_
|
||||
- `Perry Young <https://github.com/yrrepy>`_
|
||||
|
|
@ -7,6 +7,7 @@ Release Notes
|
|||
.. toctree::
|
||||
:maxdepth: 1
|
||||
|
||||
0.15.0
|
||||
0.14.0
|
||||
0.13.3
|
||||
0.13.2
|
||||
|
|
|
|||
|
|
@ -114,8 +114,9 @@ settings_file.particles = particles
|
|||
|
||||
# Create an initial uniform spatial source distribution over fissionable zones
|
||||
bounds = [-1, -1, -1, 1, 1, 1]
|
||||
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
|
||||
settings_file.source = openmc.IndependentSource(space=uniform_dist)
|
||||
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:])
|
||||
settings_file.source = openmc.IndependentSource(
|
||||
space=uniform_dist, constraints={'fissionable': True})
|
||||
|
||||
settings_file.keff_trigger = {'type' : 'std_dev', 'threshold' : 5E-4}
|
||||
settings_file.trigger_active = True
|
||||
|
|
|
|||
|
|
@ -124,8 +124,9 @@ settings_file.particles = particles
|
|||
|
||||
# Create an initial uniform spatial source distribution over fissionable zones
|
||||
bounds = [-1, -1, -1, 1, 1, 1]
|
||||
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
|
||||
settings_file.source = openmc.IndependentSource(space=uniform_dist)
|
||||
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:])
|
||||
settings_file.source = openmc.IndependentSource(
|
||||
space=uniform_dist, constraints={'fissionable': True})
|
||||
|
||||
settings_file.export_to_xml()
|
||||
|
||||
|
|
|
|||
|
|
@ -115,8 +115,9 @@ settings_file.particles = particles
|
|||
|
||||
# Create an initial uniform spatial source distribution over fissionable zones
|
||||
bounds = [-1, -1, -1, 1, 1, 1]
|
||||
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
|
||||
settings_file.source = openmc.IndependentSource(space=uniform_dist)
|
||||
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:])
|
||||
settings_file.source = openmc.IndependentSource(
|
||||
space=uniform_dist, constraints={'fissionable': True})
|
||||
|
||||
settings_file.trigger_active = True
|
||||
settings_file.trigger_max_batches = 100
|
||||
|
|
|
|||
|
|
@ -67,8 +67,9 @@ settings.particles = 1000
|
|||
# Create an initial uniform spatial source distribution over fissionable zones
|
||||
lower_left = (-pitch/2, -pitch/2, -1)
|
||||
upper_right = (pitch/2, pitch/2, 1)
|
||||
uniform_dist = openmc.stats.Box(lower_left, upper_right, only_fissionable=True)
|
||||
settings.source = openmc.IndependentSource(space=uniform_dist)
|
||||
uniform_dist = openmc.stats.Box(lower_left, upper_right)
|
||||
settings.source = openmc.IndependentSource(
|
||||
space=uniform_dist, constraints={'fissionable': True})
|
||||
|
||||
# For source convergence checks, add a mesh that can be used to calculate the
|
||||
# Shannon entropy
|
||||
|
|
|
|||
|
|
@ -113,8 +113,9 @@ settings.particles = 1000
|
|||
# Create an initial uniform spatial source distribution over fissionable zones
|
||||
lower_left = (-pitch/2, -pitch/2, -1)
|
||||
upper_right = (pitch/2, pitch/2, 1)
|
||||
uniform_dist = openmc.stats.Box(lower_left, upper_right, only_fissionable=True)
|
||||
settings.source = openmc.IndependentSource(space=uniform_dist)
|
||||
uniform_dist = openmc.stats.Box(lower_left, upper_right)
|
||||
settings.source = openmc.IndependentSource(
|
||||
space=uniform_dist, constraints={'fissionable': True})
|
||||
settings.export_to_xml()
|
||||
|
||||
###############################################################################
|
||||
|
|
|
|||
|
|
@ -10,7 +10,7 @@ namespace openmc {
|
|||
constexpr int VERSION_MAJOR {@OPENMC_VERSION_MAJOR@};
|
||||
constexpr int VERSION_MINOR {@OPENMC_VERSION_MINOR@};
|
||||
constexpr int VERSION_RELEASE {@OPENMC_VERSION_RELEASE@};
|
||||
constexpr bool VERSION_DEV {true};
|
||||
constexpr bool VERSION_DEV {false};
|
||||
constexpr std::array<int, 3> VERSION {VERSION_MAJOR, VERSION_MINOR, VERSION_RELEASE};
|
||||
// clang-format on
|
||||
|
||||
|
|
|
|||
|
|
@ -39,4 +39,4 @@ from .config import *
|
|||
from openmc.model import Model
|
||||
|
||||
|
||||
__version__ = '0.14.1-dev'
|
||||
__version__ = '0.15.0'
|
||||
|
|
|
|||
|
|
@ -786,7 +786,7 @@ class Integrator(ABC):
|
|||
path : PathLike
|
||||
Path to file to write. Defaults to 'depletion_results.h5'.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
"""
|
||||
with change_directory(self.operator.output_dir):
|
||||
n = self.operator.initial_condition()
|
||||
|
|
@ -993,7 +993,7 @@ class SIIntegrator(Integrator):
|
|||
path : PathLike
|
||||
Path to file to write. Defaults to 'depletion_results.h5'.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
"""
|
||||
with change_directory(self.operator.output_dir):
|
||||
n = self.operator.initial_condition()
|
||||
|
|
|
|||
|
|
@ -219,7 +219,7 @@ class MicroXS:
|
|||
sections available. MicroXS entry will be 0 if the nuclide cross section
|
||||
is not found.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Parameters
|
||||
----------
|
||||
|
|
|
|||
|
|
@ -174,7 +174,7 @@ class Mesh(_FortranObjectWithID):
|
|||
) -> List[List[Tuple[Material, float]]]:
|
||||
"""Determine volume of materials in each mesh element
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Parameters
|
||||
----------
|
||||
|
|
@ -231,7 +231,7 @@ class Mesh(_FortranObjectWithID):
|
|||
) -> np.ndarray:
|
||||
"""Get mesh bin indices for a rasterized plot.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Parameters
|
||||
----------
|
||||
|
|
|
|||
|
|
@ -157,7 +157,7 @@ class MeshBase(IDManagerMixin, ABC):
|
|||
) -> List[openmc.Material]:
|
||||
"""Generate homogenized materials over each element in a mesh.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Parameters
|
||||
----------
|
||||
|
|
@ -1487,6 +1487,8 @@ class CylindricalMesh(StructuredMesh):
|
|||
) -> Tuple[int, int, int]:
|
||||
"""Finds the index of the mesh voxel at the specified x,y,z coordinates.
|
||||
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Parameters
|
||||
----------
|
||||
coords : Sequence[float]
|
||||
|
|
|
|||
|
|
@ -169,7 +169,7 @@ def plot_xs(reactions, divisor_types=None, temperature=294., axis=None,
|
|||
energy_axis_units : {'eV', 'keV', 'MeV'}
|
||||
Units used on the plot energy axis
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Returns
|
||||
-------
|
||||
|
|
|
|||
|
|
@ -344,7 +344,7 @@ class Region(ABC):
|
|||
def plot(self, *args, **kwargs):
|
||||
"""Display a slice plot of the region.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Parameters
|
||||
----------
|
||||
|
|
|
|||
|
|
@ -113,7 +113,7 @@ class Settings:
|
|||
max_particle_events : int
|
||||
Maximum number of allowed particle events per source particle.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
max_order : None or int
|
||||
Maximum scattering order to apply globally when in multi-group mode.
|
||||
max_history_splits : int
|
||||
|
|
@ -158,7 +158,7 @@ class Settings:
|
|||
Starting ray distribution (must be uniform in space and angle) as
|
||||
specified by a :class:`openmc.SourceBase` object.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
resonance_scattering : dict
|
||||
Settings for resonance elastic scattering. Accepted keys are 'enable'
|
||||
(bool), 'method' (str), 'energy_min' (float), 'energy_max' (float), and
|
||||
|
|
|
|||
|
|
@ -264,7 +264,7 @@ class IndependentSource(SourceBase):
|
|||
Domains to reject based on, i.e., if a sampled spatial location is not
|
||||
within one of these domains, it will be rejected.
|
||||
|
||||
.. deprecated:: 0.14.1
|
||||
.. deprecated:: 0.15.0
|
||||
Use the `constraints` argument instead.
|
||||
constraints : dict
|
||||
Constraints on sampled source particles. Valid keys include 'domains',
|
||||
|
|
@ -482,7 +482,7 @@ class MeshSource(SourceBase):
|
|||
strength of the mesh source as a whole is the sum of all source strengths
|
||||
applied to the elements.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Parameters
|
||||
----------
|
||||
|
|
@ -1049,7 +1049,7 @@ def write_source_file(
|
|||
def read_source_file(filename: PathLike) -> typing.List[SourceParticle]:
|
||||
"""Read a source file and return a list of source particles.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Parameters
|
||||
----------
|
||||
|
|
|
|||
|
|
@ -769,7 +769,7 @@ class Box(Spatial):
|
|||
Whether spatial sites should only be accepted if they occur in
|
||||
fissionable materials
|
||||
|
||||
.. deprecated:: 0.14.1
|
||||
.. deprecated:: 0.15.0
|
||||
Use the `constraints` argument when defining a source object instead.
|
||||
|
||||
Attributes
|
||||
|
|
@ -782,7 +782,7 @@ class Box(Spatial):
|
|||
Whether spatial sites should only be accepted if they occur in
|
||||
fissionable materials
|
||||
|
||||
.. deprecated:: 0.14.1
|
||||
.. deprecated:: 0.15.0
|
||||
Use the `constraints` argument when defining a source object instead.
|
||||
|
||||
"""
|
||||
|
|
|
|||
|
|
@ -22,7 +22,7 @@ class Trigger(EqualityMixin):
|
|||
can cause the trigger to fire prematurely if there are zero scores in
|
||||
any bin at the first evaluation.
|
||||
|
||||
.. versionadded:: 0.14.1
|
||||
.. versionadded:: 0.15.0
|
||||
|
||||
Attributes
|
||||
----------
|
||||
|
|
|
|||
|
|
@ -49,9 +49,12 @@
|
|||
<batches>15</batches>
|
||||
<inactive>5</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<seed>1</seed>
|
||||
</settings>
|
||||
|
|
|
|||
|
|
@ -142,8 +142,9 @@ def model():
|
|||
core_radius,
|
||||
core_height / 2.0,
|
||||
]
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
|
||||
model.settings.source = openmc.IndependentSource(space=distribution)
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:])
|
||||
model.settings.source = openmc.IndependentSource(
|
||||
space=distribution, constraints={'fissionable': True})
|
||||
|
||||
# =============================================================================
|
||||
# Tallies
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>8</surface_ids>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4</surface_ids>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>1 2 3</surface_ids>
|
||||
|
|
|
|||
|
|
@ -21,9 +21,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-4 -4 -20 4 4 20</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -21,9 +21,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-4 -4 -20 4 4 20</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>1</surface_ids>
|
||||
|
|
|
|||
|
|
@ -21,9 +21,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-4 -4 -20 4 4 20</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -21,9 +21,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-4 -4 -20 4 4 20</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>1</surface_ids>
|
||||
|
|
|
|||
|
|
@ -21,9 +21,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-4 -4 -20 4 4 20</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -21,9 +21,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-4 -4 -20 4 4 20</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-4 -4 -20 4 4 20</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>101 102 103 104 105 106</surface_ids>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-4 -4 -20 4 4 20</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>101 102 103 104 105 106</surface_ids>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -42,9 +42,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<max_particles>300</max_particles>
|
||||
|
|
|
|||
|
|
@ -35,9 +35,12 @@
|
|||
<batches>5</batches>
|
||||
<inactive>1</inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="fission">
|
||||
<space type="box">
|
||||
<parameters>-2.0 -2.0 -2.0 2.0 2.0 2.0</parameters>
|
||||
</space>
|
||||
<constraints>
|
||||
<fissionable>true</fissionable>
|
||||
</constraints>
|
||||
</source>
|
||||
<surf_source_write>
|
||||
<surface_ids>4 5 6 7 8 9</surface_ids>
|
||||
|
|
|
|||
|
|
@ -277,8 +277,9 @@ def model_1():
|
|||
core_radius,
|
||||
core_height / 2.0,
|
||||
]
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
|
||||
model.settings.source = openmc.IndependentSource(space=distribution)
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:])
|
||||
model.settings.source = openmc.IndependentSource(
|
||||
space=distribution, constraints={'fissionable': True})
|
||||
|
||||
return model
|
||||
|
||||
|
|
@ -379,8 +380,9 @@ def model_2():
|
|||
core_radius,
|
||||
core_height / 2.0,
|
||||
]
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
|
||||
model.settings.source = openmc.IndependentSource(space=distribution)
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:])
|
||||
model.settings.source = openmc.IndependentSource(
|
||||
space=distribution, constraints={'fissionable': True})
|
||||
|
||||
return model
|
||||
|
||||
|
|
@ -481,8 +483,9 @@ def model_3():
|
|||
core_radius,
|
||||
core_height / 2.0,
|
||||
]
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
|
||||
model.settings.source = openmc.IndependentSource(space=distribution)
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:])
|
||||
model.settings.source = openmc.IndependentSource(
|
||||
space=distribution, constraints={'fissionable': True})
|
||||
|
||||
return model
|
||||
|
||||
|
|
@ -594,8 +597,9 @@ def model_4():
|
|||
core_radius,
|
||||
core_height / 2.0,
|
||||
]
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
|
||||
model.settings.source = openmc.IndependentSource(space=distribution)
|
||||
distribution = openmc.stats.Box(bounds[:3], bounds[3:])
|
||||
model.settings.source = openmc.IndependentSource(
|
||||
space=distribution, constraints={'fissionable': True})
|
||||
|
||||
return model
|
||||
|
||||
|
|
@ -935,8 +939,9 @@ def model_dagmc_1():
|
|||
model.settings.inactive = 1
|
||||
model.settings.seed = 1
|
||||
|
||||
source_box = openmc.stats.Box([-4, -4, -20], [4, 4, 20], only_fissionable=True)
|
||||
model.settings.source = openmc.IndependentSource(space=source_box)
|
||||
source_box = openmc.stats.Box([-4, -4, -20], [4, 4, 20])
|
||||
model.settings.source = openmc.IndependentSource(
|
||||
space=source_box, constraints={'fissionable': True})
|
||||
|
||||
return model
|
||||
|
||||
|
|
@ -1069,8 +1074,9 @@ def model_dagmc_2():
|
|||
model.settings.inactive = 1
|
||||
model.settings.seed = 1
|
||||
|
||||
source_box = openmc.stats.Box([-4, -4, -20], [4, 4, 20], only_fissionable=True)
|
||||
model.settings.source = openmc.IndependentSource(space=source_box)
|
||||
source_box = openmc.stats.Box([-4, -4, -20], [4, 4, 20])
|
||||
model.settings.source = openmc.IndependentSource(
|
||||
space=source_box, constraints={'fissionable': True})
|
||||
|
||||
return model
|
||||
|
||||
|
|
|
|||
|
|
@ -168,7 +168,7 @@ def test_restart_track(run_in_tmpdir, sphere_model):
|
|||
|
||||
# generate lost particle files
|
||||
with pytest.raises(RuntimeError, match='Maximum number of lost particles has been reached.'):
|
||||
sphere_model.run(output=False)
|
||||
sphere_model.run(output=False, threads=1)
|
||||
|
||||
lost_particle_files = list(Path.cwd().glob('particle_*.h5'))
|
||||
assert len(lost_particle_files) > 0
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue