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Doc typo fix for rand ray mgxs (#3280)
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Co-authored-by: Jon Shimwell <jon@proximafusion.com>
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shimwell and jon-proximafusion authored Jan 28, 2025
1 parent 27f3afe commit 860d739
Showing 1 changed file with 4 additions and 5 deletions.
9 changes: 4 additions & 5 deletions docs/source/usersguide/random_ray.rst
Original file line number Diff line number Diff line change
Expand Up @@ -111,7 +111,7 @@ detector from the core. In this case, rays sampled in the moderator region and
heading toward the detector will begin life with a highly scattered thermal
spectrum and will have an inaccurate fast spectrum. If the dead zone length is
only 20 cm, we might imagine such rays writing to the detector tally within
their active lengths, despite their innaccurate estimate of the uncollided fast
their active lengths, despite their inaccurate estimate of the uncollided fast
angular flux. Thus, an inactive length of 100--200 cm would ensure that any such
rays would still be within their inactive regions, and only rays that have
actually traversed through the core (and thus have an accurate representation of
Expand Down Expand Up @@ -487,7 +487,7 @@ two group energy decomposition::
mgxs_lib = openmc.mgxs.Library(geometry)

# Pick energy group structure
groups = mgxs.EnergyGroups(mgxs.GROUP_STRUCTURES['CASMO-2'])
groups = openmc.mgxs.EnergyGroups(openmc.mgxs.GROUP_STRUCTURES['CASMO-2'])
mgxs_lib.energy_groups = groups

# Disable transport correction
Expand All @@ -501,7 +501,7 @@ two group energy decomposition::
mgxs_lib.domain_type = "material"

# Specify the cell domains over which to compute multi-group cross sections
mgxs_lib.domains = geom.get_all_materials().values()
mgxs_lib.domains = geometry.get_all_materials().values()

# Do not compute cross sections on a nuclide-by-nuclide basis
mgxs_lib.by_nuclide = False
Expand Down Expand Up @@ -531,7 +531,6 @@ a statepoint file (e.g., ``statepoint.100.h5``) file and summary file (e.g.,
``summary.h5``) that resulted from running our previous example::

import openmc
import openmc.mgxs as mgxs

summary = openmc.Summary('summary.h5')
geom = summary.geometry
Expand All @@ -540,7 +539,7 @@ a statepoint file (e.g., ``statepoint.100.h5``) file and summary file (e.g.,
statepoint_filename = 'statepoint.100.h5'
sp = openmc.StatePoint(statepoint_filename)

groups = mgxs.EnergyGroups(mgxs.GROUP_STRUCTURES['CASMO-2'])
groups = openmc.mgxs.EnergyGroups(openmc.mgxs.GROUP_STRUCTURES['CASMO-2'])
mgxs_lib = openmc.mgxs.Library(geom)
mgxs_lib.energy_groups = groups
mgxs_lib.correction = None
Expand Down

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