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Merge pull request #1965 from shimwell/minor_docs_typo_fix
fixed minor typo in docs
2 parents f8488e5 + 04b5f4b commit 0c2b284

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16 files changed

+45
-45
lines changed

16 files changed

+45
-45
lines changed

openmc/cell.py

Lines changed: 2 additions & 2 deletions
Original file line numberDiff line numberDiff line change
@@ -193,7 +193,7 @@ def volume(self):
193193
def atoms(self):
194194
if self._atoms is None:
195195
if self._volume is None:
196-
msg = ('Cannot calculate atom content becouse no volume '
196+
msg = ('Cannot calculate atom content because no volume '
197197
'is set. Use Cell.volume to provide it or perform '
198198
'a stochastic volume calculation.')
199199
raise ValueError(msg)
@@ -350,7 +350,7 @@ def volume(self, volume):
350350
self._volume = volume
351351

352352
# Info about atom content can now be invalid
353-
# (sice volume has just changed)
353+
# (since volume has just changed)
354354
self._atoms = None
355355

356356
def add_volume_information(self, volume_calc):

openmc/cmfd.py

Lines changed: 6 additions & 6 deletions
Original file line numberDiff line numberDiff line change
@@ -262,7 +262,7 @@ class CMFDRun:
262262
Attributes
263263
----------
264264
tally_begin : int
265-
Batch number at which CMFD tallies should begin accummulating
265+
Batch number at which CMFD tallies should begin accumulating
266266
solver_begin: int
267267
Batch number at which CMFD solver should start executing
268268
ref_d : list of floats
@@ -271,13 +271,13 @@ class CMFDRun:
271271
Dictionary indicating which CMFD results to output. Note that CMFD
272272
k-effective will always be outputted. Acceptable keys are:
273273
274-
* "balance" - Whether to output RMS [%] of the resdiual from the
274+
* "balance" - Whether to output RMS [%] of the residual from the
275275
neutron balance equation on CMFD tallies (bool)
276276
* "dominance" - Whether to output the estimated dominance ratio from
277277
the CMFD iterations (bool)
278278
* "entropy" - Whether to output the *entropy* of the CMFD predicted
279279
fission source (bool)
280-
* "source" - Whether to ouput the RMS [%] between the OpenMC fission
280+
* "source" - Whether to output the RMS [%] between the OpenMC fission
281281
source and CMFD fission source (bool)
282282
283283
downscatter : bool
@@ -315,7 +315,7 @@ class CMFDRun:
315315
adjoint_type : {'physical', 'math'}
316316
Stores type of adjoint calculation that should be performed.
317317
``run_adjoint`` must be true for an adjoint calculation to be
318-
perfomed. Options are:
318+
performed. Options are:
319319
320320
* "physical" - Create adjoint matrices from physical parameters of
321321
CMFD problem
@@ -887,7 +887,7 @@ def finalize(self):
887887
information.
888888
889889
"""
890-
# Finalize simuation
890+
# Finalize simulation
891891
openmc.lib.simulation_finalize()
892892

893893
if openmc.lib.master():
@@ -1431,7 +1431,7 @@ def _calc_fission_source(self):
14311431
nx, ny, nz, ng = self._indices
14321432
n = self._mat_dim
14331433

1434-
# Compute cmfd_src in a vecotorized manner by phi to the spatial
1434+
# Compute cmfd_src in a vectorized manner by phi to the spatial
14351435
# indices of the actual problem so that cmfd_flux can be multiplied by
14361436
# nfissxs
14371437

openmc/element.py

Lines changed: 4 additions & 4 deletions
Original file line numberDiff line numberDiff line change
@@ -54,8 +54,8 @@ def expand(self, percent, percent_type, enrichment=None,
5454
percent_type : {'ao', 'wo'}
5555
'ao' for atom percent and 'wo' for weight percent
5656
enrichment : float, optional
57-
Enrichment of an enrichment_taget nuclide in percent (ao or wo).
58-
If enrichment_taget is not supplied then it is enrichment for U235
57+
Enrichment of an enrichment_target nuclide in percent (ao or wo).
58+
If enrichment_target is not supplied then it is enrichment for U235
5959
in weight percent. For example, input 4.95 for 4.95 weight percent
6060
enriched U. Default is None (natural composition).
6161
enrichment_target: str, optional
@@ -149,7 +149,7 @@ def expand(self, percent, percent_type, enrichment=None,
149149
mutual_nuclides = sorted(list(mutual_nuclides))
150150
absent_nuclides = sorted(list(absent_nuclides))
151151

152-
# If all naturally ocurring isotopes are present in the library,
152+
# If all naturally occurring isotopes are present in the library,
153153
# add them based on their abundance
154154
if len(absent_nuclides) == 0:
155155
for nuclide in mutual_nuclides:
@@ -277,7 +277,7 @@ def expand(self, percent, percent_type, enrichment=None,
277277
tail_fraction = 1.0 - enrichment / 100.0
278278

279279
# Enrich all nuclides
280-
# Do bogus operation for enrichment target but overwrite immediatly
280+
# Do bogus operation for enrichment target but overwrite immediately
281281
# to avoid if statement in the loop
282282
for nuclide, fraction in abundances.items():
283283
abundances[nuclide] = tail_fraction * fraction / non_enriched

openmc/filter.py

Lines changed: 7 additions & 7 deletions
Original file line numberDiff line numberDiff line change
@@ -89,7 +89,7 @@ class Filter(IDManagerMixin, metaclass=FilterMeta):
8989
----------
9090
bins : Integral or Iterable of Integral or Iterable of Real
9191
The bins for the filter. This takes on different meaning for different
92-
filters. See the docstrings for sublcasses of this filter or the online
92+
filters. See the docstrings for subclasses of this filter or the online
9393
documentation for more details.
9494
filter_id : int
9595
Unique identifier for the filter
@@ -177,7 +177,7 @@ def from_hdf5(cls, group, **kwargs):
177177
filter_id = int(group.name.split('/')[-1].lstrip('filter '))
178178

179179
# If the HDF5 'type' variable matches this class's short_name, then
180-
# there is no overriden from_hdf5 method. Pass the bins to __init__.
180+
# there is no overridden from_hdf5 method. Pass the bins to __init__.
181181
if group['type'][()].decode() == cls.short_name.lower():
182182
out = cls(group['bins'][()], filter_id=filter_id)
183183
out._num_bins = group['n_bins'][()]
@@ -254,7 +254,7 @@ def from_xml_element(cls, elem, **kwargs):
254254
filter_type = elem.get('type')
255255

256256
# If the filter type matches this class's short_name, then
257-
# there is no overriden from_xml_element method
257+
# there is no overridden from_xml_element method
258258
if filter_type == cls.short_name.lower():
259259
# Get bins from element -- the default here works for any filters
260260
# that just store a list of bins that can be represented as integers
@@ -438,7 +438,7 @@ def check_bins(self, bins):
438438

439439

440440
class UniverseFilter(WithIDFilter):
441-
"""Bins tally event locations based on the Universe they occured in.
441+
"""Bins tally event locations based on the Universe they occurred in.
442442
443443
Parameters
444444
----------
@@ -462,7 +462,7 @@ class UniverseFilter(WithIDFilter):
462462

463463

464464
class MaterialFilter(WithIDFilter):
465-
"""Bins tally event locations based on the Material they occured in.
465+
"""Bins tally event locations based on the Material they occurred in.
466466
467467
Parameters
468468
----------
@@ -486,7 +486,7 @@ class MaterialFilter(WithIDFilter):
486486

487487

488488
class CellFilter(WithIDFilter):
489-
"""Bins tally event locations based on the Cell they occured in.
489+
"""Bins tally event locations based on the Cell they occurred in.
490490
491491
Parameters
492492
----------
@@ -1945,7 +1945,7 @@ def from_tabulated1d(cls, tab1d):
19451945
raise ValueError('Only Tabulated1Ds with a single interpolation '
19461946
'region are supported')
19471947
if tab1d.interpolation[0] != 2:
1948-
raise ValueError('Only linear-linar Tabulated1Ds are supported')
1948+
raise ValueError('Only linear-linear Tabulated1Ds are supported')
19491949

19501950
return cls(tab1d.x, tab1d.y)
19511951

openmc/lattice.py

Lines changed: 2 additions & 2 deletions
Original file line numberDiff line numberDiff line change
@@ -106,7 +106,7 @@ def from_hdf5(group, universes):
106106
elif lattice_type == 'hexagonal':
107107
return openmc.HexLattice.from_hdf5(group, universes)
108108
else:
109-
raise ValueError(f'Unkown lattice type: {lattice_type}')
109+
raise ValueError(f'Unknown lattice type: {lattice_type}')
110110

111111
def get_unique_universes(self):
112112
"""Determine all unique universes in the lattice
@@ -1215,7 +1215,7 @@ def universes(self, universes):
12151215
for rings in self._universes:
12161216
if len(rings) != self._num_rings:
12171217
msg = 'HexLattice ID={0:d} has an inconsistent number of ' \
1218-
'rings per axial positon'.format(self._id)
1218+
'rings per axial position'.format(self._id)
12191219
raise ValueError(msg)
12201220

12211221
else:

openmc/material.py

Lines changed: 4 additions & 4 deletions
Original file line numberDiff line numberDiff line change
@@ -443,7 +443,7 @@ def add_macroscopic(self, macroscopic):
443443

444444
# Generally speaking, the density for a macroscopic object will
445445
# be 1.0. Therefore, lets set density to 1.0 so that the user
446-
# doesnt need to set it unless its needed.
446+
# doesn't need to set it unless its needed.
447447
# Of course, if the user has already set a value of density,
448448
# then we will not override it.
449449
if self._density is None:
@@ -482,8 +482,8 @@ def add_element(self, element, percent, percent_type='ao', enrichment=None,
482482
'ao' for atom percent and 'wo' for weight percent. Defaults to atom
483483
percent.
484484
enrichment : float, optional
485-
Enrichment of an enrichment_taget nuclide in percent (ao or wo).
486-
If enrichment_taget is not supplied then it is enrichment for U235
485+
Enrichment of an enrichment_target nuclide in percent (ao or wo).
486+
If enrichment_target is not supplied then it is enrichment for U235
487487
in weight percent. For example, input 4.95 for 4.95 weight percent
488488
enriched U.
489489
Default is None (natural composition).
@@ -625,7 +625,7 @@ def add_elements_from_formula(self, formula, percent_type='ao', enrichment=None,
625625
raise ValueError(msg)
626626
elif token not in ['(', ')', ''] and not token.isdigit():
627627
msg = 'Formula must be made from a sequence of ' \
628-
'element symbols, integers, and backets. ' \
628+
'element symbols, integers, and brackets. ' \
629629
'{} is not an allowable entry.'.format(token)
630630
raise ValueError(msg)
631631

openmc/mesh.py

Lines changed: 1 addition & 1 deletion
Original file line numberDiff line numberDiff line change
@@ -144,7 +144,7 @@ class RegularMesh(MeshBase):
144144
The lower-left corner of the structured mesh. If only two coordinate
145145
are given, it is assumed that the mesh is an x-y mesh.
146146
upper_right : Iterable of float
147-
The upper-right corner of the structrued mesh. If only two coordinate
147+
The upper-right corner of the structured mesh. If only two coordinate
148148
are given, it is assumed that the mesh is an x-y mesh.
149149
width : Iterable of float
150150
The width of mesh cells in each direction.

openmc/mgxs_library.py

Lines changed: 1 addition & 1 deletion
Original file line numberDiff line numberDiff line change
@@ -477,7 +477,7 @@ def num_azimuthal(self, num_azimuthal):
477477

478478
def add_temperature(self, temperature):
479479
"""This method re-sizes the attributes of this XSdata object so that it
480-
can accomodate an additional temperature. Note that the set_* methods
480+
can accommodate an additional temperature. Note that the set_* methods
481481
will still need to be executed.
482482
483483
Parameters

openmc/plots.py

Lines changed: 5 additions & 5 deletions
Original file line numberDiff line numberDiff line change
@@ -220,7 +220,7 @@ class Plot(IDManagerMixin):
220220
mask_background : Iterable of int or str
221221
Color to apply to all cells/materials not listed in mask_components
222222
show_overlaps : bool
223-
Inidicate whether or not overlapping regions are shown
223+
Indicate whether or not overlapping regions are shown
224224
overlap_color : Iterable of int or str
225225
Color to apply to overlapping regions
226226
colors : dict
@@ -565,9 +565,9 @@ def highlight_domains(self, geometry, domains, seed=1,
565565
seed : int
566566
The random number seed used to generate the color scheme
567567
alpha : float
568-
The value between 0 and 1 to apply in alpha compisiting
568+
The value between 0 and 1 to apply in alpha compositing
569569
background : 3-tuple of int or str
570-
The background color to apply in alpha compisiting
570+
The background color to apply in alpha compositing
571571
572572
"""
573573

@@ -883,9 +883,9 @@ def highlight_domains(self, geometry, domains, seed=1,
883883
seed : int
884884
The random number seed used to generate the color scheme
885885
alpha : float
886-
The value between 0 and 1 to apply in alpha compisiting
886+
The value between 0 and 1 to apply in alpha compositing
887887
background : 3-tuple of int or str
888-
The background color to apply in alpha compisiting
888+
The background color to apply in alpha compositing
889889
890890
"""
891891

openmc/plotter.py

Lines changed: 1 addition & 1 deletion
Original file line numberDiff line numberDiff line change
@@ -882,7 +882,7 @@ def _calculate_mgxs_elem_mat(this, types, library, orders=None,
882882
else:
883883
T = temperature
884884

885-
# Check to see if we have nuclides/elements or a macrocopic object
885+
# Check to see if we have nuclides/elements or a macroscopic object
886886
if this._macroscopic is not None:
887887
# We have macroscopics
888888
nuclides = {this._macroscopic: (this._macroscopic, this.density)}

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