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Clean up includes and spacing

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This commit is contained in:
Colin Josey 2017-05-22 19:00:05 -04:00
parent 8bf8d9561b
commit fc2b3ee511
5 changed files with 9 additions and 35 deletions
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9
2x2-periodic/build-depleted.py
View file

@ -1,14 +1,9 @@
#!/usr/bin/env python3
from collections import OrderedDict
import copy
import os
import numpy as np
import openmc
import opendeplete
from geometry import beavrs, openmc_geometry
from geometry import openmc_geometry
# FIXME: Automatically extract info needed to calculate burnable cell volumes
@ -31,7 +26,7 @@ for cell in fuel_cells:
cell.fill = [old_fill.clone() for i in range(n)]
for i in range(n):
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].depletable = True
cell.fill[i].temperature = 300.0

9
2x2-reflector/build-depleted.py
View file

@ -1,14 +1,9 @@
#!/usr/bin/env python3
from collections import OrderedDict
import copy
import os
import numpy as np
import openmc
import opendeplete
from geometry import beavrs, openmc_geometry
from geometry import openmc_geometry
# FIXME: Automatically extract info needed to calculate burnable cell volumes
@ -31,7 +26,7 @@ for cell in fuel_cells:
cell.fill = [old_fill.clone() for i in range(n)]
for i in range(n):
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].depletable = True
cell.fill[i].temperature = 300.0

9
assembly/build-depleted.py
View file

@ -1,14 +1,9 @@
#!/usr/bin/env python3
from collections import OrderedDict
import copy
import os
import numpy as np
import openmc
import opendeplete
from geometry import beavrs, openmc_geometry
from geometry import openmc_geometry
# FIXME: Automatically extract info needed to calculate burnable cell volumes
@ -31,7 +26,7 @@ for cell in fuel_cells:
cell.fill = [old_fill.clone() for i in range(n)]
for i in range(n):
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].depletable = True
cell.fill[i].temperature = 300.0

9
pin-cell/build-depleted.py
View file

@ -1,14 +1,9 @@
#!/usr/bin/env python3
from collections import OrderedDict
import copy
import os
import numpy as np
import openmc
import opendeplete
from geometry import beavrs, openmc_geometry
from geometry import openmc_geometry
# FIXME: Automatically extract info needed to calculate burnable cell volumes
@ -31,7 +26,7 @@ for cell in fuel_cells:
cell.fill = [old_fill.clone() for i in range(n)]
for i in range(n):
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].depletable = True
cell.fill[i].temperature = 300.0

8
smr/build-depleted.py
View file

@ -1,14 +1,8 @@
#!/usr/bin/env python3
from collections import OrderedDict
import copy
import os
import numpy as np
import openmc
import opendeplete
from smr.materials import materials
from smr.surfaces import lattice_pitch, bottom_fuel_stack, top_active_core
from smr.core import geometry
@ -49,7 +43,7 @@ for cell in fuel_cells:
cell.fill = [old_fill.clone() for i in range(n)]
for i in range(n):
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].volume = np.pi * radius**2 * height
cell.fill[i].depletable = True
cell.fill[i].temperature = 300.0