old_contents: import openmc
  import openmc.deplete
  import matplotlib.pyplot as plt
  
  ###############################################################################
  #                      Load previous simulation results
  ###############################################################################
  
  # Load geometry from statepoint
  statepoint = 'statepoint.100.h5'
  with openmc.StatePoint(statepoint) as sp:
      geometry = sp.summary.geometry
  
  # Load previous depletion results
  previous_results = openmc.deplete.ResultsList("depletion_results.h5")
  
  ###############################################################################
  #                      Transport calculation settings
  ###############################################################################
  
  # Instantiate a Settings object, set all runtime parameters
  settings = openmc.Settings()
  settings.batches = 100
  settings.inactive = 10
  settings.particles = 10000
  
  # Create an initial uniform spatial source distribution over fissionable zones
  bounds = [-0.62992, -0.62992, -1, 0.62992, 0.62992, 1]
  uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
  settings.source = openmc.source.Source(space=uniform_dist)
  
  entropy_mesh = openmc.RegularMesh()
  entropy_mesh.lower_left = [-0.39218, -0.39218, -1.e50]
  entropy_mesh.upper_right = [0.39218, 0.39218, 1.e50]
  entropy_mesh.dimension = [10, 10, 1]
  settings.entropy_mesh = entropy_mesh
  
  ###############################################################################
  #                   Initialize and run depletion calculation
  ###############################################################################
  
  # Create depletion "operator"
  chain_file = './chain_simple.xml'
  op = openmc.deplete.Operator(geometry, settings, chain_file, previous_results)
  
  # Perform simulation using the predictor algorithm
  time_steps = [1.0, 1.0, 1.0, 1.0, 1.0]  # days
  power = 174  # W/cm, for 2D simulations only (use W for 3D)
  integrator = openmc.deplete.PredictorIntegrator(op, time_steps, power, timestep_units='d')
  integrator.integrate()
  
  ###############################################################################
  #                    Read depletion calculation results
  ###############################################################################
  
  # Open results file
  results = openmc.deplete.ResultsList.from_hdf5("depletion_results.h5")
  
  # Obtain K_eff as a function of time
  time, keff = results.get_eigenvalue()
  
  # Obtain U235 concentration as a function of time
  time, n_U235 = results.get_atoms('1', 'U235')
  
  # Obtain Xe135 capture reaction rate as a function of time
  time, Xe_capture = results.get_reaction_rate('1', 'Xe135', '(n,gamma)')
  
  ###############################################################################
  #                            Generate plots
  ###############################################################################
  
  days = 24*60*60
  plt.figure()
  plt.plot(time/days, keff, label="K-effective")
  plt.xlabel("Time (days)")
  plt.ylabel("Keff")
  plt.show()
  
  plt.figure()
  plt.plot(time/days, n_U235, label="U 235")
  plt.xlabel("Time (days)")
  plt.ylabel("n U5 (-)")
  plt.show()
  
  plt.figure()
  plt.plot(time/days, Xe_capture, label="Xe135 capture")
  plt.xlabel("Time (days)")
  plt.ylabel("RR (-)")
  plt.show()
  plt.close('all')
  
new_contents: import openmc
  import openmc.deplete
  import matplotlib.pyplot as plt
  
  ###############################################################################
  #                      Load previous simulation results
  ###############################################################################
  
  # Load geometry from statepoint
  statepoint = 'statepoint.100.h5'
  with openmc.StatePoint(statepoint) as sp:
      geometry = sp.summary.geometry
  
  # Load previous depletion results
  previous_results = openmc.deplete.ResultsList.from_hdf5("depletion_results.h5")
  
  ###############################################################################
  #                      Transport calculation settings
  ###############################################################################
  
  # Instantiate a Settings object, set all runtime parameters
  settings = openmc.Settings()
  settings.batches = 100
  settings.inactive = 10
  settings.particles = 10000
  
  # Create an initial uniform spatial source distribution over fissionable zones
  bounds = [-0.62992, -0.62992, -1, 0.62992, 0.62992, 1]
  uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
  settings.source = openmc.source.Source(space=uniform_dist)
  
  entropy_mesh = openmc.RegularMesh()
  entropy_mesh.lower_left = [-0.39218, -0.39218, -1.e50]
  entropy_mesh.upper_right = [0.39218, 0.39218, 1.e50]
  entropy_mesh.dimension = [10, 10, 1]
  settings.entropy_mesh = entropy_mesh
  
  ###############################################################################
  #                   Initialize and run depletion calculation
  ###############################################################################
  
  # Create depletion "operator"
  chain_file = './chain_simple.xml'
  op = openmc.deplete.Operator(geometry, settings, chain_file, previous_results)
  
  # Perform simulation using the predictor algorithm
  time_steps = [1.0, 1.0, 1.0, 1.0, 1.0]  # days
  power = 174  # W/cm, for 2D simulations only (use W for 3D)
  integrator = openmc.deplete.PredictorIntegrator(op, time_steps, power, timestep_units='d')
  integrator.integrate()
  
  ###############################################################################
  #                    Read depletion calculation results
  ###############################################################################
  
  # Open results file
  results = openmc.deplete.ResultsList.from_hdf5("depletion_results.h5")
  
  # Obtain K_eff as a function of time
  time, keff = results.get_eigenvalue()
  
  # Obtain U235 concentration as a function of time
  time, n_U235 = results.get_atoms('1', 'U235')
  
  # Obtain Xe135 capture reaction rate as a function of time
  time, Xe_capture = results.get_reaction_rate('1', 'Xe135', '(n,gamma)')
  
  ###############################################################################
  #                            Generate plots
  ###############################################################################
  
  days = 24*60*60
  plt.figure()
  plt.plot(time/days, keff, label="K-effective")
  plt.xlabel("Time (days)")
  plt.ylabel("Keff")
  plt.show()
  
  plt.figure()
  plt.plot(time/days, n_U235, label="U 235")
  plt.xlabel("Time (days)")
  plt.ylabel("n U5 (-)")
  plt.show()
  
  plt.figure()
  plt.plot(time/days, Xe_capture, label="Xe135 capture")
  plt.xlabel("Time (days)")
  plt.ylabel("RR (-)")
  plt.show()
  plt.close('all')
  
subject: fix ResultsList construction in pincell_depletion restart example