Merge branch 'develop' into photon-alund

This commit is contained in:
Paul Romano 2018-03-11 13:10:00 -05:00
commit 460452d4f7
746 changed files with 17707 additions and 10855 deletions

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@ -91,18 +91,6 @@ Many of the above classes are derived from several abstract classes:
openmc.Region
openmc.Lattice
Two helper function are also available to create rectangular and hexagonal
prisms defined by the intersection of four and six surface half-spaces,
respectively.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.get_hexagonal_prism
openmc.get_rectangular_prism
.. _pythonapi_tallies:
Constructing Tallies

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@ -1,6 +1,6 @@
---------------------------------------------------
:data:`openmc.capi` -- Python bindings to the C API
---------------------------------------------------
--------------------------------------------------
:mod:`openmc.capi` -- Python bindings to the C API
--------------------------------------------------
.. automodule:: openmc.capi
@ -12,18 +12,25 @@ Functions
: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
calculate_volumes
finalize
find_cell
find_material
hard_reset
init
iter_batches
keff
load_nuclide
next_batch
num_realizations
plot_geometry
reset
run
run_in_memory
simulation_init
simulation_finalize
source_bank
statepoint_write
Classes
-------
@ -33,9 +40,9 @@ Classes
:nosignatures:
:template: myclass.rst
openmc.capi.Cell
openmc.capi.EnergyFilter
openmc.capi.MaterialFilter
openmc.capi.Material
openmc.capi.Nuclide
openmc.capi.Tally
Cell
EnergyFilter
MaterialFilter
Material
Nuclide
Tally

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@ -35,9 +35,12 @@ Core Functions
:template: myfunction.rst
openmc.data.atomic_mass
openmc.data.gnd_name
openmc.data.linearize
openmc.data.thin
openmc.data.water_density
openmc.data.write_compact_458_library
openmc.data.zam
Angle-Energy Distributions
--------------------------

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@ -0,0 +1,85 @@
.. _pythonapi_deplete:
----------------------------------
:mod:`openmc.deplete` -- Depletion
----------------------------------
.. module:: openmc.deplete
Two functions are provided that implement different time-integration algorithms
for depletion calculations.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
integrator.predictor
integrator.cecm
Each of these functions expects a "transport operator" to be passed. An operator
specific to OpenMC is available using the following class:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
Operator
When running in parallel using `mpi4py <http://mpi4py.scipy.org>`_, the MPI
intercommunicator used can be changed by modifying the following module
variable. If it is not explicitly modified, it defaults to
``mpi4py.MPI.COMM_WORLD``.
.. data:: comm
MPI intercommunicator used to call OpenMC library
:type: mpi4py.MPI.Comm
Internal Classes and Functions
------------------------------
During a depletion calculation, the depletion chain, reaction rates, and number
densities are managed through a series of internal classes that are not normally
visible to a user. However, should you find yourself wondering about these
classes (e.g., if you want to know what decay modes or reactions are present in
a depletion chain), they are documented here. The following classes store data
for a depletion chain:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
Chain
DecayTuple
Nuclide
ReactionTuple
The following classes are used during a depletion simulation and store auxiliary
data, such as number densities and reaction rates for each material.
.. autosummary::
:toctree: generated
:nosignatures:
:template: myclass.rst
AtomNumber
OperatorResult
ReactionRates
Results
ResultsList
TransportOperator
Each of the integrator functions also relies on a number of "helper" functions
as follows:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
integrator.CRAM16
integrator.CRAM48

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@ -15,14 +15,15 @@ there are many substantial benefits to using the Python API, including:
- The ability to define dimensions using variables.
- Availability of standard-library modules for working with files.
- An entire ecosystem of third-party packages for scientific computing.
- Ability to create materials based on natural elements or uranium enrichment
- Automated multi-group cross section generation (:mod:`openmc.mgxs`)
- A fully-featured nuclear data interface (:mod:`openmc.data`)
- Depletion capability (:mod:`openmc.deplete`)
- Convenience functions (e.g., a function returning a hexagonal region)
- Ability to plot individual universes as geometry is being created
- A :math:`k_\text{eff}` search function (:func:`openmc.search_for_keff`)
- Random sphere packing for generating TRISO particle locations
(:func:`openmc.model.pack_trisos`)
- A fully-featured nuclear data interface (:mod:`openmc.data`)
- Ability to create materials based on natural elements or uranium enrichment
For those new to Python, there are many good tutorials available online. We
recommend going through the modules from `Codecademy
@ -40,13 +41,14 @@ Modules
-------
.. toctree::
:maxdepth: 2
:maxdepth: 1
base
stats
mgxs
model
examples
deplete
mgxs
stats
data
capi
examples
openmoc

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@ -2,6 +2,19 @@
:mod:`openmc.model` -- Model Building
-------------------------------------
Convenience Functions
---------------------
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.model.borated_water
openmc.model.get_hexagonal_prism
openmc.model.get_rectangular_prism
openmc.model.subdivide
TRISO Fuel Modeling
-------------------