Merge pull request #1691 from paulromano/sourcesite-python

Generation of source files from Python
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Patrick Shriwise 2020-10-21 16:42:42 -05:00 committed by GitHub
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7 changed files with 164 additions and 12 deletions

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@ -15,7 +15,7 @@ is that documented here.
:Datasets:
- **source_bank** (Compound type) -- Source bank information for each
particle. The compound type has fields ``wgt``, ``xyz``, ``uvw``,
``E``, ``delayed_group``, and ``particle``, which represent the
weight, position, direction, energy, energy group, delayed group,
and type of the source particle, respectively.
particle. The compound type has fields ``r``, ``u``, ``E``,
``wgt``, ``delayed_group``, and ``particle``, which represent the
position, direction, energy, weight, delayed group, and particle
type (0=neutron, 1=photon, 2=electron, 3=positron), respectively.

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@ -51,11 +51,11 @@ The current version of the statepoint file format is 17.0.
- **global_tallies** (*double[][2]*) -- Accumulated sum and
sum-of-squares for each global tally.
- **source_bank** (Compound type) -- Source bank information for each
particle. The compound type has fields ``wgt``, ``xyz``, ``uvw``,
``E``, ``g``, and ``delayed_group``, which represent the weight,
position, direction, energy, energy group, and delayed_group of the
source particle, respectively. Only present when `run_mode` is
'eigenvalue'.
particle. The compound type has fields ``r``, ``u``, ``E``,
``wgt``, ``delayed_group``, and ``particle``, which represent the
position, direction, energy, weight, delayed group, and particle
type (0=neutron, 1=photon, 2=electron, 3=positron), respectively.
Only present when `run_mode` is 'eigenvalue'.
**/tallies/**

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@ -22,9 +22,19 @@ Simulation Settings
:template: myclass.rst
openmc.Source
openmc.SourceParticle
openmc.VolumeCalculation
openmc.Settings
The following function can be used for generating a source file:
.. autosummary::
:toctree: generated
:nosignatures:
:template: myfunction.rst
openmc.write_source_file
Material Specification
----------------------