mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 06:05:58 -04:00
Added the ability to divide by a type, so now we can easily (and not with complicated routines within calculate_xs) get nu-scatter/scatter, nu-fission/fission and something like a moderating ratio (just needs xi).
This commit is contained in:
Adam Nelson
parent
739dd53c9b
commit
3f610d03ca
1 changed files with 44 additions and 15 deletions
|
|
@ -31,7 +31,7 @@ DENSITY_UNITS = ['g/cm3', 'g/cc', 'kg/cm3', 'atom/b-cm', 'atom/cm3', 'sum',
|
|||
|
||||
# Supported keywords for material xs plotting
|
||||
_PLOT_TYPES = ['total', 'scatter', 'elastic', 'inelastic', 'fission',
|
||||
'absorption', 'capture', 'nu-fission', 'nu-scatter']
|
||||
'absorption', 'capture', 'nu-fission', 'nu-scatter', 'unity']
|
||||
|
||||
# MTs to combine to generate associated plot_types
|
||||
_PLOT_TYPES_MT = {'total': (1,), 'scatter': (1, 27), 'elastic': (2,),
|
||||
|
|
@ -44,7 +44,8 @@ _PLOT_TYPES_MT = {'total': (1,), 'scatter': (1, 27), 'elastic': (2,),
|
|||
163, 164, 165, 166, 167, 168, 169, 170, 171,
|
||||
172, 173, 174, 175, 176, 177, 178, 179, 180,
|
||||
181, 183, 184, 190, 194, 196, 198, 199, 200,
|
||||
875, 891)}
|
||||
875, 891),
|
||||
'unity': (0,)}
|
||||
# Operations to use when combining MTs the first np.add is used in reference
|
||||
# to zero
|
||||
_PLOT_TYPES_OP = {'total': (np.add,), 'scatter': (np.add, np.subtract),
|
||||
|
|
@ -64,7 +65,8 @@ _PLOT_TYPES_OP = {'total': (np.add,), 'scatter': (np.add, np.subtract),
|
|||
np.add, np.add, np.add, np.add, np.add,
|
||||
np.add, np.add, np.add, np.add, np.add,
|
||||
np.add, np.add, np.add, np.add, np.add,
|
||||
np.add)}
|
||||
np.add),
|
||||
'unity': (np.add,)}
|
||||
# Whether or not to multiply the reaction by the yield as well
|
||||
_PLOT_TYPES_YIELD = {'total': (False,), 'scatter': (False, False),
|
||||
'elastic': (False,), 'inelastic': (False, False, False),
|
||||
|
|
@ -82,7 +84,8 @@ _PLOT_TYPES_YIELD = {'total': (False,), 'scatter': (False, False),
|
|||
True, True, True, True, True,
|
||||
True, True, True, True, True,
|
||||
True, True, True, True, True,
|
||||
True)}
|
||||
True),
|
||||
'unity': (False,)}
|
||||
|
||||
|
||||
class Material(object):
|
||||
|
|
@ -727,17 +730,20 @@ class Material(object):
|
|||
|
||||
return nuclides
|
||||
|
||||
def plot_xs(self, library, types, temperature=294., Erange=(1.E-5, 20.E6)):
|
||||
def plot_xs(self, library, types, divisor_types=None, temperature=294.,
|
||||
Erange=(1.E-5, 20.E6)):
|
||||
"""Creates a figure of macroscopic cross sections for this material
|
||||
|
||||
Parameters
|
||||
----------
|
||||
library : openmc.data.DataLibrary
|
||||
Library of data to use for plotting.
|
||||
types : Iterable of {'total', 'scatter', 'elastic', 'inelastic', 'fission', 'absorption'}
|
||||
The type of cross sections to include in the plot. In addition to
|
||||
the above, a custom string can be used which includes MT numbers
|
||||
and operations to perform such as '2 + 3'
|
||||
types : Iterable of values of _PLOT_TYPES
|
||||
The type of cross sections to include in the plot.
|
||||
divisor_types : Iterable of values of _PLOT_TYPES, optional
|
||||
Cross section types which will divide those produced by types before
|
||||
plotting. A type of 'unity' can be used to effectively not divide
|
||||
some types.
|
||||
temperature : float, optional
|
||||
Temperature in Kelvin to plot. If not specified, a default
|
||||
temperature of 294K will be plotted. Note that the nearest
|
||||
|
|
@ -755,6 +761,26 @@ class Material(object):
|
|||
|
||||
E, data = self.calculate_xs(library, types, temperature)
|
||||
|
||||
if divisor_types:
|
||||
cv.check_length('divisor types', divisor_types, len(types),
|
||||
len(types))
|
||||
Ediv, data_div = self.calculate_xs(library, divisor_types,
|
||||
temperature)
|
||||
|
||||
# Create a new union grid, interpolate data and data_div on to that
|
||||
# grid, and then do the actual division
|
||||
Enum = E[:]
|
||||
E = np.union1d(Enum, Ediv)
|
||||
data_new = np.zeros((len(types), len(E)))
|
||||
# import pdb; pdb.set_trace()
|
||||
for l in range(len(types)):
|
||||
data_new[l, :] = \
|
||||
np.divide(np.interp(E, Enum, data[l, :]),
|
||||
np.interp(E, Ediv, data_div[l, :]))
|
||||
if divisor_types[l] != 'unity':
|
||||
types[l] = types[l] + ' / ' + divisor_types[l]
|
||||
data = data_new
|
||||
|
||||
# Generate the plot
|
||||
fig = plt.figure()
|
||||
ax = fig.add_subplot(111)
|
||||
|
|
@ -785,10 +811,8 @@ class Material(object):
|
|||
----------
|
||||
library : openmc.data.DataLibrary
|
||||
Library of data to use for plotting.
|
||||
types : Iterable of {'total', 'scatter', 'elastic', 'inelastic', 'fission', 'absorption'}
|
||||
The type of cross sections to include in the plot. In addition to
|
||||
the above, a custom string can be used which includes MT numbers
|
||||
and operations to perform such as '2 + 3'
|
||||
types : Iterable of values of _PLOT_TYPES
|
||||
The type of cross sections to include in the plot.
|
||||
temperature : float, optional
|
||||
Temperature in Kelvin to plot. If not specified, a default
|
||||
temperature of 294K will be plotted. Note that the nearest
|
||||
|
|
@ -966,6 +990,8 @@ class Material(object):
|
|||
funcs.append(nuc[mt].xs[nucT])
|
||||
else:
|
||||
funcs.append(nuc[mt].xs[nucT])
|
||||
elif mt == 0:
|
||||
funcs.append(lambda x: 1.)
|
||||
else:
|
||||
funcs.append(lambda x: 0.)
|
||||
xs[-1].append(openmc.data.Combination(funcs, op))
|
||||
|
|
@ -981,8 +1007,11 @@ class Material(object):
|
|||
# Now we can combine all the nuclidic data
|
||||
data = np.zeros((len(mts), len(unionE)))
|
||||
for l in range(len(mts)):
|
||||
for n in range(len(nuclides)):
|
||||
data[l, :] += nuc_densities[n] * xs[n][l](unionE)
|
||||
if types[l] == 'unity':
|
||||
data[l, :] = 1.
|
||||
else:
|
||||
for n in range(len(nuclides)):
|
||||
data[l, :] += nuc_densities[n] * xs[n][l](unionE)
|
||||
|
||||
return unionE, data
|
||||
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue