Merge is inevitable because of new test created and test suite was changed

Merge branch 'develop' into test_surface_tallies
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guillaume 2017-08-06 14:15:48 -04:00
commit c0efbf13c5
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.. _capi:
=====
C API
=====
.. c:function:: void openmc_calculate_voumes()
Run a stochastic volume calculation
.. c:function:: int openmc_cell_get_id(int32_t index, int32_t* id)
Get the ID of a cell
:param index: Index in the cells array
:type index: int32_t
:param id: ID of the cell
:type id: int32_t*
:return: Return status (negative if an error occurred)
:rtype: int
.. c:function:: int openmc_cell_set_temperature(index index, double T, int32_t* instance)
Set the temperature of a cell.
:param index: Index in the cells array
:type index: int32_t
:param T: Temperature in Kelvin
:type T: double
:param instance: Which instance of the cell. To set the temperature for all
instances, pass a null pointer.
:type instance: int32_t*
:return: Return status (negative if an error occurred)
:rtype: int
.. c:function:: void openmc_finalize()
Finalize a simulation
.. c:function:: void openmc_find(double* xyz, int rtype, int32_t* id, int32_t* instance)
Determine the ID of the cell/material containing a given point
:param xyz: Cartesian coordinates
:type xyz: double[3]
:param rtype: Which ID to return (1=cell, 2=material)
:type rtype: int
:param id: ID of the cell/material found. If a material is requested and the
point is in a void, the ID is 0. If an error occurs, the ID is -1.
:type id: int32_t*
:param instance: If a cell is repetaed in the geometry, the instance of the
cell that was found and zero otherwise.
:type instance: int32_t*
.. c:function:: int openmc_get_cell(int32_t id, int32_t* index)
Get the index in the cells array for a cell with a given ID
:param id: ID of the cell
:type id: int32_t
:param index: Index in the cells array
:type index: int32_t*
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: int openmc_get_keff(double k_combined[])
:param k_combined: Combined estimate of k-effective
:type k_combined: double[2]
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: int openmc_get_nuclide(char name[], int* index)
Get the index in the nuclides array for a nuclide with a given name
:param name: Name of the nuclide
:type name: char[]
:param index: Index in the nuclides array
:type index: int*
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: int openmc_get_tally(int32_t id, int32_t* index)
Get the index in the tallies array for a tally with a given ID
:param id: ID of the tally
:type id: int32_t
:param index: Index in the tallies array
:type index: int32_t*
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: int openmc_get_material(int32_t id, int32_t* index)
Get the index in the materials array for a material with a given ID
:param id: ID of the material
:type id: int32_t
:param index: Index in the materials array
:type index: int32_t*
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: void openmc_hard_reset()
Reset tallies, timers, and pseudo-random number generator state
.. c:function:: void openmc_init(int intracomm)
Initialize OpenMC
:param intracomm: MPI intracommunicator
:type intracomm: int
.. c:function:: int openmc_load_nuclide(char name[])
Load data for a nuclide from the HDF5 data library.
:param name: Name of the nuclide.
:type name: char[]
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: int openmc_material_add_nuclide(int32_t index, char name[], double density)
Add a nuclide to an existing material. If the nuclide already exists, the
density is overwritten.
:param index: Index in the materials array
:type index: int32_t
:param name: Name of the nuclide
:type name: char[]
:param density: Density in atom/b-cm
:type density: double
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: int openmc_material_get_densities(int32_t index, int* nuclides[], double* densities[])
Get density for each nuclide in a material.
:param index: Index in the materials array
:type index: int32_t
:param nuclides: Pointer to array of nuclide indices
:type nuclides: int**
:param densities: Pointer to the array of densities
:type densities: double**
:param n: Length of the array
:type n: int
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: int openmc_material_get_id(int32_t index, int32_t* id)
Get the ID of a material
:param index: Index in the materials array
:type index: int32_t
:param id: ID of the material
:type id: int32_t*
:return: Return status (negative if an error occurred)
:rtype: int
.. c:function:: int openmc_material_set_density(int32_t index, double density)
Set the density of a material.
:param index: Index in the materials array
:type index: int32_t
:param density: Density of the material in atom/b-cm
:type density: double
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: int openmc_material_set_densities(int32_t, n, char* name[], double density[])
:param index: Index in the materials array
:type index: int32_t
:param n: Length of name/density
:type n: int
:param name: Array of nuclide names
:type name: char**
:param density: Array of densities
:type density: double[]
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: int openmc_nuclide_name(int index, char* name[])
Get name of a nuclide
:param index: Index in the nuclides array
:type index: int
:param name: Name of the nuclide
:type name: char**
:return: Return status (negative if an error occurs)
:rtype: int
.. c:function:: void openmc_plot_geometry()
Run plotting mode.
.. c:function:: void openmc_reset()
Resets all tally scores
.. c:function:: void openmc_run()
Run a simulation
.. c:function:: int openmc_tally_get_id(int32_t index, int32_t* id)
Get the ID of a tally
:param index: Index in the tallies array
:type index: int32_t
:param id: ID of the tally
:type id: int32_t*
:return: Return status (negative if an error occurred)
:rtype: int
.. c:function:: int openmc_tally_get_nuclides(int32_t index, int* nuclides[], int* n)
Get nuclides specified in a tally
:param index: Index in the tallies array
:type index: int32_t
:param nuclides: Array of nuclide indices
:type nuclides: int**
:param n: Number of nuclides
:type n: int*
:return: Return status (negative if an error occurred)
:rtype: int
.. c:function:: int openmc_tally_results(int32_t index, double** ptr, int shape_[3])
Get a pointer to tally results array.
:param index: Index in the tallies array
:type index: int32_t
:param ptr: Pointer to the results array
:type ptr: double**
:param shape_: Shape of the results array
:type shape_: int[3]
:return: Return status (negative if an error occurred)
:rtype: int
.. c:function:: int openmc_tally_set_nuclides(int32_t index, int n, char* nuclides[])
Set the nuclides for a tally
:param index: Index in the tallies array
:type index: int32_t
:param n: Number of nuclides
:type n: int
:param nuclides: Array of nuclide names
:type nuclides: char**
:return: Return status (negative if an error occurred)
:rtype: int

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@ -25,8 +25,9 @@ except ImportError:
MOCK_MODULES = ['numpy', 'numpy.polynomial', 'numpy.polynomial.polynomial',
'h5py', 'pandas', 'uncertainties', 'openmoc',
'openmc.data.reconstruct']
'numpy.ctypeslib', 'scipy', 'scipy.sparse', 'scipy.interpolate',
'scipy.integrate', 'scipy.optimize', 'scipy.special', 'h5py',
'pandas', 'uncertainties', 'openmoc', 'openmc.data.reconstruct']
sys.modules.update((mod_name, MagicMock()) for mod_name in MOCK_MODULES)
import numpy as np

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@ -36,6 +36,7 @@ free to send a message to the User's Group `mailing list`_.
usersguide/index
devguide/index
pythonapi/index
capi/index
io_formats/index
publications
license

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@ -107,9 +107,13 @@ Each ``material`` element can have the following attributes or sub-elements:
multi-group :ref:`energy_mode`.
:sab:
Associates an S(a,b) table with the material. This element has one
Associates an S(a,b) table with the material. This element has an
attribute/sub-element called ``name``. The ``name`` attribute
is the name of the S(a,b) table that should be associated with the material.
There is also an optional ``fraction`` element which indicates what fraction
of the relevant nuclides will be affected by the S(a,b) table (e.g. which
fraction of a material is crystalline versus amorphous). ``fraction``
defaults to unity.
*Default*: None

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@ -661,6 +661,17 @@ methods like "nearest" and "interpolation" in the resolved resonance range.
*Default*: False
-------------------------------
``<temperature_range>`` Element
-------------------------------
The ``<temperature_range>`` element specifies a minimum and maximum temperature
in Kelvin above and below which cross sections should be loaded for all nuclides
and thermal scattering tables. This can be used for multi-physics simulations
where the temperatures might change from one iteration to the next.
*Default*: None
.. _temperature_tolerance:
-----------------------------------

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---------------------------------------------------
:data:`openmc.capi` -- Python bindings to the C API
---------------------------------------------------
.. automodule:: openmc.capi
Functions
---------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.capi.calculate_volumes
openmc.capi.finalize
openmc.capi.find_cell
openmc.capi.find_material
openmc.capi.hard_reset
openmc.capi.init
openmc.capi.keff
openmc.capi.load_nuclide
openmc.capi.plot_geometry
openmc.capi.reset
openmc.capi.run
openmc.capi.run_in_memory
Classes
-------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
openmc.capi.CellView
openmc.capi.MaterialView
openmc.capi.NuclideView
openmc.capi.TallyView

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@ -47,5 +47,6 @@ Modules
mgxs
model
data
capi
examples
openmoc

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@ -19,7 +19,7 @@ surface is a locus of zeros of a function of Cartesian coordinates
:math:`x,y,z`, e.g.
- A plane perpendicular to the :math:`x` axis: :math:`x - x_0 = 0`
- A cylinder perpendicular to the :math:`z` axis: :math:`(x - x_0)^2 + (y -
- A cylinder parallel to the :math:`z` axis: :math:`(x - x_0)^2 + (y -
y_0)^2 - R^2 = 0`
- A sphere: :math:`(x - x_0)^2 + (y - y_0)^2 + (z - z_0)^2 - R^2 = 0`

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@ -401,14 +401,6 @@ distributions.
NumPy is used extensively within the Python API for its powerful
N-dimensional array.
`h5py <http://www.h5py.org/>`_
h5py provides Python bindings to the HDF5 library. Since OpenMC outputs
various HDF5 files, h5py is needed to provide access to data within these
files from Python.
.. admonition:: Optional
:class: note
`SciPy <https://www.scipy.org/>`_
SciPy's special functions, sparse matrices, and spatial data structures
are used for several optional features in the API.
@ -417,6 +409,14 @@ distributions.
Pandas is used to generate tally DataFrames as demonstrated in
:ref:`examples_pandas` example notebook.
`h5py <http://www.h5py.org/>`_
h5py provides Python bindings to the HDF5 library. Since OpenMC outputs
various HDF5 files, h5py is needed to provide access to data within these
files from Python.
.. admonition:: Optional
:class: note
`Matplotlib <http://matplotlib.org/>`_
Matplotlib is used to providing plotting functionality in the API like the
:meth:`Universe.plot` method and the :func:`openmc.plot_xs` function.