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added restart in predictor, working on skipping initial step if already ran

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guillaume 2018-05-29 17:45:31 -04:00
parent ed65c15b30
commit 1673b2983a
5 changed files with 72 additions and 23 deletions
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28
examples/python/pincell_depletion/restart_depletion.py
View file

@ -1,6 +1,7 @@
import openmc
import openmc.deplete
import numpy as np
import matplotlib.pyplot as plt
###############################################################################
# Simulation Input File Parameters
@ -13,7 +14,7 @@ particles = 1000
# Depletion simulation parameters
time_step = 1*24*60*60 # s
final_time = 15*24*60*60 # s
final_time = 5*24*60*60 # s
time_steps = np.full(final_time // time_step, time_step)
chain_file = './chain_simple.xml'
@ -28,14 +29,15 @@ statepoint = 'statepoint.100.h5'
sp = openmc.StatePoint(statepoint)
geometry = sp.summary.geometry
# Load previous delpletion results
# Close statepoint and summary files to be able to write over them
sp.summary._f.close()
sp._f.close()
# Load previous depletion results
previous_results = openmc.deplete.ResultsList("depletion_results.h5")
# Reload volumes into geometry
previous_results.transfer_volumes(geometry)
###############################################################################
# Set transport calculation settings
# Transport calculation settings
###############################################################################
# Instantiate a Settings object, set all runtime parameters, and export to XML
@ -59,7 +61,8 @@ settings_file.entropy_mesh = entropy_mesh
# Initialize and run depletion calculation
###############################################################################
op = openmc.deplete.Operator(geometry, settings_file, chain_file)
op = openmc.deplete.Operator(geometry, settings_file, chain_file, \
previous_results)
# Perform simulation using the predictor algorithm
openmc.deplete.integrator.predictor(op, time_steps, power)
@ -73,6 +76,13 @@ results = openmc.deplete.ResultsList("depletion_results.h5")
# Obtain K_eff as a function of time
time, keff = results.get_eigenvalue()
print(time/24/60/60)
print(keff)
# Obtain U235 concentration as a function of time
time, n_U235 = results.get_atoms('1', 'U235')
# Plot eigenvalue as a function of time
plt.figure()
plt.plot(time/24/60/60, keff, label="K-effective")
plt.xlabel("Time (day)")
plt.ylabel("Keff")
plt.show()

8
examples/python/pincell_depletion/run_depletion.py
View file

@ -13,7 +13,7 @@ particles = 1000
# Depletion simulation parameters
time_step = 1*24*60*60 # s
final_time = 15*24*60*60 # s
final_time = 5*24*60*60 # s
time_steps = np.full(final_time // time_step, time_step)
chain_file = './chain_simple.xml'
@ -94,7 +94,7 @@ root.add_cells([fuel, gap, clad, water])
geometry = openmc.Geometry(root)
###############################################################################
# Volumes of depletable materials
# Set volumes of depletable materials
###############################################################################
# Compute cell areas
@ -105,7 +105,7 @@ area[fuel] = np.pi * fuel_or.coefficients['R'] ** 2
uo2.volume = area[fuel]
###############################################################################
# Transport calculation settings
# Transport calculation settings
###############################################################################
# Instantiate a Settings object, set all runtime parameters, and export to XML
@ -135,7 +135,7 @@ op = openmc.deplete.Operator(geometry, settings_file, chain_file)
openmc.deplete.integrator.predictor(op, time_steps, power)
###############################################################################
# Read depletion calculation results
# Read depletion calculation results
###############################################################################
# Open results file