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Merge pull request #1691 from paulromano/sourcesite-python
Generation of source files from Python
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5b81083742
7 changed files with 164 additions and 12 deletions
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@ -15,7 +15,7 @@ is that documented here.
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:Datasets:
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- **source_bank** (Compound type) -- Source bank information for each
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particle. The compound type has fields ``wgt``, ``xyz``, ``uvw``,
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``E``, ``delayed_group``, and ``particle``, which represent the
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weight, position, direction, energy, energy group, delayed group,
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and type of the source particle, respectively.
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particle. The compound type has fields ``r``, ``u``, ``E``,
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``wgt``, ``delayed_group``, and ``particle``, which represent the
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position, direction, energy, weight, delayed group, and particle
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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.
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- **global_tallies** (*double[][2]*) -- Accumulated sum and
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sum-of-squares for each global tally.
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- **source_bank** (Compound type) -- Source bank information for each
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particle. The compound type has fields ``wgt``, ``xyz``, ``uvw``,
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``E``, ``g``, and ``delayed_group``, which represent the weight,
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position, direction, energy, energy group, and delayed_group of the
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source particle, respectively. Only present when `run_mode` is
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'eigenvalue'.
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particle. The compound type has fields ``r``, ``u``, ``E``,
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``wgt``, ``delayed_group``, and ``particle``, which represent the
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position, direction, energy, weight, delayed group, and particle
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type (0=neutron, 1=photon, 2=electron, 3=positron), respectively.
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Only present when `run_mode` is 'eigenvalue'.
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**/tallies/**
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@ -22,9 +22,19 @@ Simulation Settings
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:template: myclass.rst
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openmc.Source
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openmc.SourceParticle
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openmc.VolumeCalculation
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openmc.Settings
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The following function can be used for generating a source file:
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.. autosummary::
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:toctree: generated
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:nosignatures:
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:template: myfunction.rst
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openmc.write_source_file
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Material Specification
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----------------------
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