Fix deplete imports

scripts/example_geometry.py

@@ -9,8 +9,7 @@ import math
 
 import numpy as np
 import openmc
-
-from opendeplete import density_to_mat
+from openmc.deplete import density_to_mat
 
 
 def generate_initial_number_density():

scripts/example_plot.py

@@ -1,11 +1,8 @@
 """An example file showing how to plot data from a simulation."""
 
 import matplotlib.pyplot as plt
-
-from opendeplete import read_results, \
-                        evaluate_single_nuclide, \
-                        evaluate_reaction_rate, \
-                        evaluate_eigenvalue
+from openmc.deplete import (read_results, evaluate_single_nuclide,
+                            evaluate_reaction_rate, evaluate_eigenvalue)
 
 # Set variables for where the data is, and what we want to read out.
 result_folder = "test"

scripts/example_run.py

@@ -1,7 +1,7 @@
 """An example file showing how to run a simulation."""
 
 import numpy as np
-import opendeplete
+import openmc.deplete
 
 import example_geometry
 
@@ -16,7 +16,7 @@ N = np.floor(dt2/dt1)
 dt = np.repeat([dt1], N)
 
 # Create settings variable
-settings = opendeplete.OpenMCSettings()
+settings = openmc.deplete.OpenMCSettings()
 
 settings.openmc_call = "openmc"
 # An example for mpiexec:
@@ -33,7 +33,7 @@ settings.power = 2.337e15*4*joule_per_mev  # MeV/second cm from CASMO
 settings.dt_vec = dt
 settings.output_dir = 'test'
 
-op = opendeplete.OpenMCOperator(geometry, settings)
+op = openmc.deplete.OpenMCOperator(geometry, settings)
 
 # Perform simulation using the MCNPX/MCNP6 algorithm
-opendeplete.integrator.cecm(op)
+openmc.deplete.integrator.cecm(op)

scripts/make_chain.py

@@ -6,7 +6,7 @@ from zipfile import ZipFile
 
 import requests
 from tqdm import tqdm
-import opendeplete
+import openmc.deplete
 
 
 urls = [
@@ -52,7 +52,7 @@ def main():
     nfy_files = glob.glob(os.path.join('nfy', '*.endf'))
     neutron_files = glob.glob(os.path.join('neutrons', '*.endf'))
 
-    chain = opendeplete.DepletionChain.from_endf(decay_files, nfy_files, neutron_files)
+    chain = openmc.deplete.DepletionChain.from_endf(decay_files, nfy_files, neutron_files)
     chain.xml_write('chain_endfb71.xml')