mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-26 21:25:36 -04:00
Cosmetic fixes from PullRequest [2019-12-05]
This commit is contained in:
parent
8fcd74b14b
commit
6d0aa86cef
39 changed files with 247 additions and 222 deletions
|
|
@ -12,7 +12,7 @@ PLOT_TYPES = ['total', 'scatter', 'elastic', 'inelastic', 'fission',
|
|||
'absorption', 'capture', 'nu-fission', 'nu-scatter', 'unity',
|
||||
'slowing-down power', 'damage']
|
||||
|
||||
# Supported keywoards for multi-group cross section plotting
|
||||
# Supported keywords for multi-group cross section plotting
|
||||
PLOT_TYPES_MGXS = ['total', 'absorption', 'scatter', 'fission',
|
||||
'kappa-fission', 'nu-fission', 'prompt-nu-fission',
|
||||
'deleyed-nu-fission', 'chi', 'chi-prompt', 'chi-delayed',
|
||||
|
|
@ -245,7 +245,7 @@ def calculate_cexs(this, data_type, types, temperature=294., sab_name=None,
|
|||
----------
|
||||
this : {str, openmc.Nuclide, openmc.Element, openmc.Material}
|
||||
Object to source data from
|
||||
data_type : {'nuclide', 'element', material'}
|
||||
data_type : {'nuclide', 'element', 'material'}
|
||||
Type of object to plot
|
||||
types : Iterable of values of PLOT_TYPES
|
||||
The type of cross sections to calculate
|
||||
|
|
@ -619,7 +619,7 @@ def calculate_mgxs(this, data_type, types, orders=None, temperature=294.,
|
|||
----------
|
||||
this : str or openmc.Material
|
||||
Object to source data from
|
||||
data_type : {'nuclide', 'element', material', 'macroscopic'}
|
||||
data_type : {'nuclide', 'element', 'material', 'macroscopic'}
|
||||
Type of object to plot
|
||||
types : Iterable of values of PLOT_TYPES_MGXS
|
||||
The type of cross sections to calculate
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue