import openmc.deplete
from math import pi
import matplotlib.pyplot as plt
First create a simple one material, one region problem and deplete it over three 1-day timesteps.
material = openmc.Material()
material.add_nuclide('U235', 1.0)
material.set_density('g/cm3', 5.0)
material.volume = 4/3 * pi * 10.0**3
model = openmc.Model()
sph = openmc.Sphere(r=10.0, boundary_type='vacuum')
cell = openmc.Cell(fill=material, region=-sph)
model.geometry = openmc.Geometry([cell])
model.settings = openmc.Settings()
model.settings.particles = 1000
model.settings.batches = 50
model.settings.inactive = 10
chain_file = 'chain_simple.xml'
op = openmc.deplete.Operator(model, chain_file)
power = 40.0e3
time_steps = [1.0]*3
integrator = openmc.deplete.PredictorIntegrator(op, time_steps, timestep_units='d', power=power)
integrator.integrate()
%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%% ############### %%%%%%%%%%%%%%%%%%%%%%%% ################## %%%%%%%%%%%%%%%%%%%%%%% ################### %%%%%%%%%%%%%%%%%%%%%%% #################### %%%%%%%%%%%%%%%%%%%%%% ##################### %%%%%%%%%%%%%%%%%%%%% ###################### %%%%%%%%%%%%%%%%%%%% ####################### %%%%%%%%%%%%%%%%%% ####################### %%%%%%%%%%%%%%%%% ###################### %%%%%%%%%%%%%%%%% #################### %%%%%%%%%%%%%%%%% ################# %%%%%%%%%%%%%%%%% ############### %%%%%%%%%%%%%%%% ############ %%%%%%%%%%%%%%% ######## %%%%%%%%%%%%%% %%%%%%%%%%% | The OpenMC Monte Carlo Code Copyright | 2011-2021 MIT, UChicago Argonne LLC, and contributors License | https://docs.openmc.org/en/latest/license.html Version | 0.13.0-dev Git SHA1 | 65b02c57b9c09cf0c4c914a31034ed076688165e Date/Time | 2022-01-09 13:43:52 OpenMP Threads | 12 Reading settings XML file... Reading cross sections XML file... Reading materials XML file... Reading geometry XML file... Reading U235 from /opt/data/hdf5/nndc_hdf5_v15/U235.h5 Minimum neutron data temperature: 294 K Maximum neutron data temperature: 294 K Preparing distributed cell instances... Reading plot XML file... Writing summary.h5 file... Reading I135 from /opt/data/hdf5/nndc_hdf5_v15/I135.h5 Reading Xe135 from /opt/data/hdf5/nndc_hdf5_v15/Xe135.h5 Reading Xe136 from /opt/data/hdf5/nndc_hdf5_v15/Xe136.h5 Reading Cs135 from /opt/data/hdf5/nndc_hdf5_v15/Cs135.h5 Reading Gd157 from /opt/data/hdf5/nndc_hdf5_v15/Gd157.h5 Reading Gd156 from /opt/data/hdf5/nndc_hdf5_v15/Gd156.h5 Reading U234 from /opt/data/hdf5/nndc_hdf5_v15/U234.h5 Reading U238 from /opt/data/hdf5/nndc_hdf5_v15/U238.h5 Maximum neutron transport energy: 20000000 eV for U235 Initializing source particles... ====================> K EIGENVALUE SIMULATION <==================== Bat./Gen. k Average k ========= ======== ==================== 1/1 0.44518 2/1 0.37906 3/1 0.35856 4/1 0.33546 5/1 0.33864 6/1 0.34190 7/1 0.32486 8/1 0.35235 9/1 0.33251 10/1 0.33518 11/1 0.32198 12/1 0.32571 0.32384 +/- 0.00187 13/1 0.33900 0.32889 +/- 0.00517 14/1 0.32974 0.32911 +/- 0.00366 15/1 0.31343 0.32597 +/- 0.00423 16/1 0.34141 0.32854 +/- 0.00430 17/1 0.33988 0.33016 +/- 0.00398 18/1 0.32317 0.32929 +/- 0.00356 19/1 0.33678 0.33012 +/- 0.00325 20/1 0.33961 0.33107 +/- 0.00305 21/1 0.32598 0.33061 +/- 0.00280 22/1 0.34779 0.33204 +/- 0.00293 23/1 0.34242 0.33284 +/- 0.00281 24/1 0.34736 0.33387 +/- 0.00280 25/1 0.32826 0.33350 +/- 0.00264 26/1 0.33177 0.33339 +/- 0.00247 27/1 0.33458 0.33346 +/- 0.00232 28/1 0.33354 0.33347 +/- 0.00219 29/1 0.33125 0.33335 +/- 0.00207 30/1 0.33253 0.33331 +/- 0.00197 31/1 0.33983 0.33362 +/- 0.00190 32/1 0.32817 0.33337 +/- 0.00182 33/1 0.33153 0.33329 +/- 0.00174 34/1 0.33852 0.33351 +/- 0.00168 35/1 0.33025 0.33338 +/- 0.00162 36/1 0.33850 0.33358 +/- 0.00157 37/1 0.33694 0.33370 +/- 0.00152 38/1 0.33765 0.33384 +/- 0.00147 39/1 0.33440 0.33386 +/- 0.00142 40/1 0.32965 0.33372 +/- 0.00138 41/1 0.33707 0.33383 +/- 0.00133 42/1 0.34793 0.33427 +/- 0.00137 43/1 0.32330 0.33394 +/- 0.00136 44/1 0.33243 0.33389 +/- 0.00132 45/1 0.32191 0.33355 +/- 0.00133 46/1 0.32493 0.33331 +/- 0.00132 47/1 0.33701 0.33341 +/- 0.00128 48/1 0.33396 0.33343 +/- 0.00125 49/1 0.34328 0.33368 +/- 0.00124 50/1 0.33067 0.33360 +/- 0.00121 Creating state point statepoint.50.h5... =======================> TIMING STATISTICS <======================= Total time for initialization = 4.7577e-02 seconds Reading cross sections = 3.9985e-02 seconds Total time in simulation = 4.8107e-02 seconds Time in transport only = 3.7646e-02 seconds Time in inactive batches = 8.3598e-03 seconds Time in active batches = 3.9747e-02 seconds Time synchronizing fission bank = 2.6843e-03 seconds Sampling source sites = 2.4146e-03 seconds SEND/RECV source sites = 2.5521e-04 seconds Time accumulating tallies = 2.9472e-03 seconds Time writing statepoints = 2.2034e-03 seconds Total time for finalization = 5.9802e-05 seconds Total time elapsed = 9.9555e-02 seconds Calculation Rate (inactive) = 1.19621e+06 particles/second Calculation Rate (active) = 1.00637e+06 particles/second ============================> RESULTS <============================ k-effective (Collision) = 0.33654 +/- 0.00174 k-effective (Track-length) = 0.33360 +/- 0.00121 k-effective (Absorption) = 0.34157 +/- 0.00442 Combined k-effective = 0.33457 +/- 0.00111 Leakage Fraction = 0.85930 +/- 0.00182 Creating state point openmc_simulation_n0.h5... Maximum neutron transport energy: 20000000 eV for U235 Initializing source particles... ====================> K EIGENVALUE SIMULATION <==================== Bat./Gen. k Average k ========= ======== ==================== 1/1 0.44339 2/1 0.37826 3/1 0.35221 4/1 0.34922 5/1 0.34501 6/1 0.33781 7/1 0.33154 8/1 0.33461 9/1 0.33471 10/1 0.33565 11/1 0.34487 12/1 0.33343 0.33915 +/- 0.00572 13/1 0.33519 0.33783 +/- 0.00356 14/1 0.33699 0.33762 +/- 0.00252 15/1 0.33378 0.33685 +/- 0.00210 16/1 0.33426 0.33642 +/- 0.00177 17/1 0.33301 0.33593 +/- 0.00157 18/1 0.34614 0.33721 +/- 0.00187 19/1 0.32589 0.33595 +/- 0.00207 20/1 0.32563 0.33492 +/- 0.00212 21/1 0.33598 0.33502 +/- 0.00192 22/1 0.34082 0.33550 +/- 0.00182 23/1 0.33245 0.33527 +/- 0.00169 24/1 0.32735 0.33470 +/- 0.00166 25/1 0.32265 0.33390 +/- 0.00174 26/1 0.33420 0.33392 +/- 0.00163 27/1 0.34306 0.33445 +/- 0.00162 28/1 0.33313 0.33438 +/- 0.00153 29/1 0.34539 0.33496 +/- 0.00156 30/1 0.33775 0.33510 +/- 0.00149 31/1 0.32327 0.33454 +/- 0.00152 32/1 0.33729 0.33466 +/- 0.00146 33/1 0.33310 0.33459 +/- 0.00139 34/1 0.32289 0.33411 +/- 0.00142 35/1 0.32959 0.33392 +/- 0.00138 36/1 0.34504 0.33435 +/- 0.00139 37/1 0.31932 0.33380 +/- 0.00145 38/1 0.31966 0.33329 +/- 0.00148 39/1 0.32981 0.33317 +/- 0.00144 40/1 0.33276 0.33316 +/- 0.00139 41/1 0.33519 0.33322 +/- 0.00134 42/1 0.33414 0.33325 +/- 0.00130 43/1 0.34086 0.33348 +/- 0.00128 44/1 0.33009 0.33338 +/- 0.00125 45/1 0.32816 0.33323 +/- 0.00122 46/1 0.32060 0.33288 +/- 0.00124 47/1 0.34275 0.33315 +/- 0.00123 48/1 0.33844 0.33329 +/- 0.00121 49/1 0.32663 0.33312 +/- 0.00119 50/1 0.33314 0.33312 +/- 0.00116 Creating state point statepoint.50.h5... =======================> TIMING STATISTICS <======================= Total time for initialization = 0.0000e+00 seconds Reading cross sections = 0.0000e+00 seconds Total time in simulation = 5.2577e-02 seconds Time in transport only = 3.6513e-02 seconds Time in inactive batches = 5.9433e-03 seconds Time in active batches = 4.6634e-02 seconds Time synchronizing fission bank = 2.8639e-03 seconds Sampling source sites = 2.5966e-03 seconds SEND/RECV source sites = 2.5190e-04 seconds Time accumulating tallies = 6.8783e-03 seconds Time writing statepoints = 5.3778e-03 seconds Total time for finalization = 6.4615e-05 seconds Total time elapsed = 5.5925e-02 seconds Calculation Rate (inactive) = 1.68258e+06 particles/second Calculation Rate (active) = 857749 particles/second ============================> RESULTS <============================ k-effective (Collision) = 0.33492 +/- 0.00219 k-effective (Track-length) = 0.33312 +/- 0.00116 k-effective (Absorption) = 0.33368 +/- 0.00373 Combined k-effective = 0.33312 +/- 0.00115 Leakage Fraction = 0.86337 +/- 0.00156 Creating state point openmc_simulation_n1.h5... Maximum neutron transport energy: 20000000 eV for U235 Initializing source particles... ====================> K EIGENVALUE SIMULATION <==================== Bat./Gen. k Average k ========= ======== ==================== 1/1 0.43764 2/1 0.37151 3/1 0.35618 4/1 0.34880 5/1 0.33780 6/1 0.33063 7/1 0.34847 8/1 0.32855 9/1 0.32569 10/1 0.33595 11/1 0.33918 12/1 0.32217 0.33067 +/- 0.00850 13/1 0.32066 0.32734 +/- 0.00594 14/1 0.34358 0.33140 +/- 0.00584 15/1 0.32657 0.33043 +/- 0.00463 16/1 0.34450 0.33278 +/- 0.00445 17/1 0.34323 0.33427 +/- 0.00404 18/1 0.33571 0.33445 +/- 0.00351 19/1 0.33439 0.33444 +/- 0.00309 20/1 0.33000 0.33400 +/- 0.00280 21/1 0.32163 0.33287 +/- 0.00277 22/1 0.32287 0.33204 +/- 0.00266 23/1 0.33314 0.33213 +/- 0.00245 24/1 0.33211 0.33212 +/- 0.00227 25/1 0.33497 0.33231 +/- 0.00212 26/1 0.33975 0.33278 +/- 0.00204 27/1 0.33596 0.33297 +/- 0.00192 28/1 0.35064 0.33395 +/- 0.00206 29/1 0.33884 0.33421 +/- 0.00197 30/1 0.33380 0.33418 +/- 0.00187 31/1 0.34804 0.33484 +/- 0.00189 32/1 0.32764 0.33452 +/- 0.00184 33/1 0.33207 0.33441 +/- 0.00176 34/1 0.32265 0.33392 +/- 0.00175 35/1 0.34831 0.33450 +/- 0.00178 36/1 0.34693 0.33497 +/- 0.00177 37/1 0.32072 0.33445 +/- 0.00179 38/1 0.34476 0.33481 +/- 0.00176 39/1 0.33968 0.33498 +/- 0.00171 40/1 0.33298 0.33492 +/- 0.00165 41/1 0.34382 0.33520 +/- 0.00162 42/1 0.32851 0.33499 +/- 0.00158 43/1 0.31258 0.33431 +/- 0.00168 44/1 0.33554 0.33435 +/- 0.00163 45/1 0.32995 0.33423 +/- 0.00159 46/1 0.31969 0.33382 +/- 0.00159 47/1 0.32416 0.33356 +/- 0.00157 48/1 0.32749 0.33340 +/- 0.00154 49/1 0.31304 0.33288 +/- 0.00159 50/1 0.32534 0.33269 +/- 0.00156 Creating state point statepoint.50.h5... =======================> TIMING STATISTICS <======================= Total time for initialization = 0.0000e+00 seconds Reading cross sections = 0.0000e+00 seconds Total time in simulation = 4.9787e-02 seconds Time in transport only = 3.5364e-02 seconds Time in inactive batches = 5.6371e-03 seconds Time in active batches = 4.4150e-02 seconds Time synchronizing fission bank = 2.7776e-03 seconds Sampling source sites = 2.5122e-03 seconds SEND/RECV source sites = 2.5014e-04 seconds Time accumulating tallies = 5.2078e-03 seconds Time writing statepoints = 5.8251e-03 seconds Total time for finalization = 6.1818e-05 seconds Total time elapsed = 5.3166e-02 seconds Calculation Rate (inactive) = 1.77395e+06 particles/second Calculation Rate (active) = 905996 particles/second ============================> RESULTS <============================ k-effective (Collision) = 0.32995 +/- 0.00282 k-effective (Track-length) = 0.33269 +/- 0.00156 k-effective (Absorption) = 0.32968 +/- 0.00409 Combined k-effective = 0.33273 +/- 0.00161 Leakage Fraction = 0.86487 +/- 0.00158 Creating state point openmc_simulation_n2.h5... Maximum neutron transport energy: 20000000 eV for U235 Initializing source particles... ====================> K EIGENVALUE SIMULATION <==================== Bat./Gen. k Average k ========= ======== ==================== 1/1 0.43897 2/1 0.36752 3/1 0.33475 4/1 0.34311 5/1 0.32238 6/1 0.32624 7/1 0.32126 8/1 0.32441 9/1 0.33653 10/1 0.31893 11/1 0.31984 12/1 0.33756 0.32870 +/- 0.00886 13/1 0.33054 0.32932 +/- 0.00515 14/1 0.33394 0.33047 +/- 0.00382 15/1 0.32740 0.32986 +/- 0.00302 16/1 0.31232 0.32693 +/- 0.00383 17/1 0.33812 0.32853 +/- 0.00361 18/1 0.33259 0.32904 +/- 0.00316 19/1 0.32548 0.32864 +/- 0.00282 20/1 0.34703 0.33048 +/- 0.00312 21/1 0.33728 0.33110 +/- 0.00289 22/1 0.33859 0.33172 +/- 0.00271 23/1 0.33579 0.33204 +/- 0.00251 24/1 0.32914 0.33183 +/- 0.00234 25/1 0.33862 0.33228 +/- 0.00222 26/1 0.33775 0.33263 +/- 0.00211 27/1 0.32328 0.33208 +/- 0.00205 28/1 0.33470 0.33222 +/- 0.00194 29/1 0.33050 0.33213 +/- 0.00184 30/1 0.32773 0.33191 +/- 0.00176 31/1 0.33071 0.33185 +/- 0.00167 32/1 0.33949 0.33220 +/- 0.00163 33/1 0.33229 0.33220 +/- 0.00156 34/1 0.32804 0.33203 +/- 0.00150 35/1 0.32284 0.33166 +/- 0.00149 36/1 0.34618 0.33222 +/- 0.00153 37/1 0.33959 0.33250 +/- 0.00150 38/1 0.34136 0.33281 +/- 0.00148 39/1 0.33620 0.33293 +/- 0.00143 40/1 0.32989 0.33283 +/- 0.00139 41/1 0.33808 0.33300 +/- 0.00135 42/1 0.32021 0.33260 +/- 0.00137 43/1 0.33591 0.33270 +/- 0.00133 44/1 0.33040 0.33263 +/- 0.00129 45/1 0.33325 0.33265 +/- 0.00126 46/1 0.33018 0.33258 +/- 0.00122 47/1 0.32765 0.33245 +/- 0.00120 48/1 0.33027 0.33239 +/- 0.00117 49/1 0.32830 0.33228 +/- 0.00114 50/1 0.32343 0.33206 +/- 0.00113 Creating state point statepoint.50.h5... =======================> TIMING STATISTICS <======================= Total time for initialization = 0.0000e+00 seconds Reading cross sections = 0.0000e+00 seconds Total time in simulation = 5.4866e-02 seconds Time in transport only = 4.0356e-02 seconds Time in inactive batches = 7.1365e-03 seconds Time in active batches = 4.7730e-02 seconds Time synchronizing fission bank = 2.9047e-03 seconds Sampling source sites = 2.6269e-03 seconds SEND/RECV source sites = 2.6190e-04 seconds Time accumulating tallies = 4.7966e-03 seconds Time writing statepoints = 5.9634e-03 seconds Total time for finalization = 6.4340e-05 seconds Total time elapsed = 5.8373e-02 seconds Calculation Rate (inactive) = 1.40124e+06 particles/second Calculation Rate (active) = 838054 particles/second ============================> RESULTS <============================ k-effective (Collision) = 0.33116 +/- 0.00215 k-effective (Track-length) = 0.33206 +/- 0.00113 k-effective (Absorption) = 0.33397 +/- 0.00448 Combined k-effective = 0.33231 +/- 0.00112 Leakage Fraction = 0.86295 +/- 0.00184 Creating state point openmc_simulation_n3.h5...
Now let's look at the density of $^{135}$Xe from the results:
results = openmc.deplete.ResultsList.from_hdf5('depletion_results.h5')
time, n_Xe135 = results.get_atoms('1', 'Xe135')
days = 24*60*60
plt.plot(time/days, n_Xe135)
plt.xlabel('Time [d]')
plt.ylabel('Xe135 [atoms]')
Text(0, 0.5, 'Xe135 [atoms]')
For the next depletion run, we need to get a new set of materials that is equivalent to the last depletion step. For this, we can use the ResultsList.export_to_materials
method. The change we'll make to the material is to remove ${135}$Xe so that it starts with a near-zero concentration.
# Get materials at the end of the last simulation
model.materials = results.export_to_materials(len(time_steps))
# Now change the material by getting rid of Xe135
model.materials[0].remove_nuclide('Xe135')
Now run the depletion integrator again --- note that we don't supply previous results (which would override the material change we made above).
# We need to create a new operator; otherwise, it will still use the number densities
# from the end of the previous simulation
op = openmc.deplete.Operator(model, chain_file)
integrator = openmc.deplete.PredictorIntegrator(op, time_steps, timestep_units='d', power=power)
integrator.integrate()
%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%% %%%%%%%%%%%%%%%%%%%%%%%% ############### %%%%%%%%%%%%%%%%%%%%%%%% ################## %%%%%%%%%%%%%%%%%%%%%%% ################### %%%%%%%%%%%%%%%%%%%%%%% #################### %%%%%%%%%%%%%%%%%%%%%% ##################### %%%%%%%%%%%%%%%%%%%%% ###################### %%%%%%%%%%%%%%%%%%%% ####################### %%%%%%%%%%%%%%%%%% ####################### %%%%%%%%%%%%%%%%% ###################### %%%%%%%%%%%%%%%%% #################### %%%%%%%%%%%%%%%%% ################# %%%%%%%%%%%%%%%%% ############### %%%%%%%%%%%%%%%% ############ %%%%%%%%%%%%%%% ######## %%%%%%%%%%%%%% %%%%%%%%%%% | The OpenMC Monte Carlo Code Copyright | 2011-2021 MIT, UChicago Argonne LLC, and contributors License | https://docs.openmc.org/en/latest/license.html Version | 0.13.0-dev Git SHA1 | 65b02c57b9c09cf0c4c914a31034ed076688165e Date/Time | 2022-01-09 13:43:53 OpenMP Threads | 12 Reading settings XML file... Reading cross sections XML file... Reading materials XML file... Reading geometry XML file... Reading I135 from /opt/data/hdf5/nndc_hdf5_v15/I135.h5 Reading Xe136 from /opt/data/hdf5/nndc_hdf5_v15/Xe136.h5 Reading Cs135 from /opt/data/hdf5/nndc_hdf5_v15/Cs135.h5 Reading Gd157 from /opt/data/hdf5/nndc_hdf5_v15/Gd157.h5 Reading Gd156 from /opt/data/hdf5/nndc_hdf5_v15/Gd156.h5 Reading U234 from /opt/data/hdf5/nndc_hdf5_v15/U234.h5 Reading U235 from /opt/data/hdf5/nndc_hdf5_v15/U235.h5 Reading U238 from /opt/data/hdf5/nndc_hdf5_v15/U238.h5 Minimum neutron data temperature: 0 K Maximum neutron data temperature: 1.7976931348623157e+308 K Preparing distributed cell instances... Reading plot XML file... Writing summary.h5 file... Reading Xe135 from /opt/data/hdf5/nndc_hdf5_v15/Xe135.h5 Maximum neutron transport energy: 20000000 eV for I135 Initializing source particles... ====================> K EIGENVALUE SIMULATION <==================== Bat./Gen. k Average k ========= ======== ==================== 1/1 0.44499 2/1 0.37975 3/1 0.35298 4/1 0.34118 5/1 0.33717 6/1 0.34054 7/1 0.32571 8/1 0.33094 9/1 0.31767 10/1 0.33711 11/1 0.32746 12/1 0.33361 0.33053 +/- 0.00307 13/1 0.33729 0.33278 +/- 0.00287 14/1 0.31204 0.32760 +/- 0.00557 15/1 0.35363 0.33281 +/- 0.00676 16/1 0.32952 0.33226 +/- 0.00555 17/1 0.33687 0.33292 +/- 0.00473 18/1 0.32477 0.33190 +/- 0.00423 19/1 0.32252 0.33086 +/- 0.00387 20/1 0.33911 0.33168 +/- 0.00356 21/1 0.33617 0.33209 +/- 0.00324 22/1 0.32190 0.33124 +/- 0.00308 23/1 0.33006 0.33115 +/- 0.00284 24/1 0.32309 0.33057 +/- 0.00269 25/1 0.32976 0.33052 +/- 0.00250 26/1 0.33036 0.33051 +/- 0.00234 27/1 0.32291 0.33006 +/- 0.00224 28/1 0.33655 0.33042 +/- 0.00215 29/1 0.31822 0.32978 +/- 0.00213 30/1 0.34582 0.33058 +/- 0.00217 31/1 0.32458 0.33030 +/- 0.00209 32/1 0.32461 0.33004 +/- 0.00201 33/1 0.32295 0.32973 +/- 0.00194 34/1 0.34932 0.33055 +/- 0.00203 35/1 0.34864 0.33127 +/- 0.00208 36/1 0.34792 0.33191 +/- 0.00210 37/1 0.33887 0.33217 +/- 0.00203 38/1 0.31751 0.33165 +/- 0.00203 39/1 0.34412 0.33208 +/- 0.00200 40/1 0.32791 0.33194 +/- 0.00194 41/1 0.33789 0.33213 +/- 0.00189 42/1 0.33964 0.33236 +/- 0.00184 43/1 0.32730 0.33221 +/- 0.00179 44/1 0.33543 0.33230 +/- 0.00174 45/1 0.33573 0.33240 +/- 0.00169 46/1 0.32221 0.33212 +/- 0.00167 47/1 0.34005 0.33233 +/- 0.00164 48/1 0.33499 0.33240 +/- 0.00160 49/1 0.34347 0.33269 +/- 0.00158 50/1 0.33390 0.33272 +/- 0.00154 Creating state point statepoint.50.h5... =======================> TIMING STATISTICS <======================= Total time for initialization = 4.8436e-01 seconds Reading cross sections = 4.7836e-01 seconds Total time in simulation = 4.4880e-02 seconds Time in transport only = 3.4566e-02 seconds Time in inactive batches = 6.1937e-03 seconds Time in active batches = 3.8687e-02 seconds Time synchronizing fission bank = 2.5904e-03 seconds Sampling source sites = 2.3432e-03 seconds SEND/RECV source sites = 2.3338e-04 seconds Time accumulating tallies = 3.0039e-03 seconds Time writing statepoints = 2.1722e-03 seconds Total time for finalization = 5.6857e-05 seconds Total time elapsed = 5.3259e-01 seconds Calculation Rate (inactive) = 1.61456e+06 particles/second Calculation Rate (active) = 1.03395e+06 particles/second ============================> RESULTS <============================ k-effective (Collision) = 0.33326 +/- 0.00231 k-effective (Track-length) = 0.33272 +/- 0.00154 k-effective (Absorption) = 0.33551 +/- 0.00539 Combined k-effective = 0.33285 +/- 0.00157 Leakage Fraction = 0.86215 +/- 0.00216 Creating state point openmc_simulation_n0.h5... Maximum neutron transport energy: 20000000 eV for I135 Initializing source particles... ====================> K EIGENVALUE SIMULATION <==================== Bat./Gen. k Average k ========= ======== ==================== 1/1 0.44304 2/1 0.37678 3/1 0.35418 4/1 0.34945 5/1 0.33601 6/1 0.32262 7/1 0.32733 8/1 0.32685 9/1 0.33419 10/1 0.33031 11/1 0.32766 12/1 0.33874 0.33320 +/- 0.00554 13/1 0.33716 0.33452 +/- 0.00346 14/1 0.33721 0.33519 +/- 0.00254 15/1 0.33802 0.33576 +/- 0.00204 16/1 0.32795 0.33446 +/- 0.00212 17/1 0.33964 0.33520 +/- 0.00194 18/1 0.32893 0.33441 +/- 0.00185 19/1 0.31602 0.33237 +/- 0.00262 20/1 0.33439 0.33257 +/- 0.00235 21/1 0.34165 0.33340 +/- 0.00228 22/1 0.34085 0.33402 +/- 0.00217 23/1 0.32933 0.33366 +/- 0.00203 24/1 0.33219 0.33355 +/- 0.00188 25/1 0.33482 0.33364 +/- 0.00175 26/1 0.32928 0.33336 +/- 0.00166 27/1 0.34823 0.33424 +/- 0.00179 28/1 0.35674 0.33549 +/- 0.00210 29/1 0.33788 0.33562 +/- 0.00199 30/1 0.32127 0.33490 +/- 0.00202 31/1 0.33130 0.33473 +/- 0.00193 32/1 0.34438 0.33517 +/- 0.00189 33/1 0.33792 0.33529 +/- 0.00181 34/1 0.32681 0.33493 +/- 0.00177 35/1 0.33487 0.33493 +/- 0.00170 36/1 0.34786 0.33543 +/- 0.00170 37/1 0.33966 0.33558 +/- 0.00165 38/1 0.34130 0.33579 +/- 0.00160 39/1 0.32394 0.33538 +/- 0.00160 40/1 0.32715 0.33511 +/- 0.00157 41/1 0.34174 0.33532 +/- 0.00153 42/1 0.33771 0.33539 +/- 0.00148 43/1 0.33322 0.33533 +/- 0.00144 44/1 0.33487 0.33531 +/- 0.00140 45/1 0.32783 0.33510 +/- 0.00137 46/1 0.32464 0.33481 +/- 0.00137 47/1 0.33517 0.33482 +/- 0.00133 48/1 0.33256 0.33476 +/- 0.00129 49/1 0.32880 0.33461 +/- 0.00127 50/1 0.33417 0.33460 +/- 0.00124 Creating state point statepoint.50.h5... =======================> TIMING STATISTICS <======================= Total time for initialization = 0.0000e+00 seconds Reading cross sections = 0.0000e+00 seconds Total time in simulation = 5.4805e-02 seconds Time in transport only = 4.0073e-02 seconds Time in inactive batches = 5.6291e-03 seconds Time in active batches = 4.9176e-02 seconds Time synchronizing fission bank = 2.7622e-03 seconds Sampling source sites = 2.4806e-03 seconds SEND/RECV source sites = 2.5121e-04 seconds Time accumulating tallies = 5.3500e-03 seconds Time writing statepoints = 5.2063e-03 seconds Total time for finalization = 6.2409e-05 seconds Total time elapsed = 5.8172e-02 seconds Calculation Rate (inactive) = 1.77647e+06 particles/second Calculation Rate (active) = 813405 particles/second ============================> RESULTS <============================ k-effective (Collision) = 0.33615 +/- 0.00292 k-effective (Track-length) = 0.33460 +/- 0.00124 k-effective (Absorption) = 0.33953 +/- 0.00351 Combined k-effective = 0.33477 +/- 0.00129 Leakage Fraction = 0.86047 +/- 0.00140 Creating state point openmc_simulation_n1.h5... Maximum neutron transport energy: 20000000 eV for I135 Initializing source particles... ====================> K EIGENVALUE SIMULATION <==================== Bat./Gen. k Average k ========= ======== ==================== 1/1 0.43749 2/1 0.37037 3/1 0.35902 4/1 0.33888 5/1 0.32159 6/1 0.33254 7/1 0.33918 8/1 0.32945 9/1 0.32723 10/1 0.34119 11/1 0.33134 12/1 0.31736 0.32435 +/- 0.00699 13/1 0.31267 0.32046 +/- 0.00561 14/1 0.32451 0.32147 +/- 0.00409 15/1 0.34099 0.32537 +/- 0.00503 16/1 0.34485 0.32862 +/- 0.00523 17/1 0.34059 0.33033 +/- 0.00474 18/1 0.33071 0.33038 +/- 0.00411 19/1 0.35215 0.33280 +/- 0.00436 20/1 0.34348 0.33387 +/- 0.00404 21/1 0.32824 0.33336 +/- 0.00369 22/1 0.32528 0.33268 +/- 0.00344 23/1 0.33203 0.33263 +/- 0.00316 24/1 0.32846 0.33233 +/- 0.00294 25/1 0.33623 0.33259 +/- 0.00275 26/1 0.33216 0.33257 +/- 0.00257 27/1 0.33786 0.33288 +/- 0.00244 28/1 0.35845 0.33430 +/- 0.00270 29/1 0.34805 0.33502 +/- 0.00266 30/1 0.33342 0.33494 +/- 0.00252 31/1 0.32471 0.33445 +/- 0.00245 32/1 0.34187 0.33479 +/- 0.00236 33/1 0.33047 0.33460 +/- 0.00226 34/1 0.33385 0.33457 +/- 0.00216 35/1 0.34163 0.33485 +/- 0.00209 36/1 0.33033 0.33468 +/- 0.00202 37/1 0.33540 0.33471 +/- 0.00194 38/1 0.33524 0.33473 +/- 0.00187 39/1 0.33022 0.33457 +/- 0.00181 40/1 0.33805 0.33469 +/- 0.00176 41/1 0.33910 0.33483 +/- 0.00170 42/1 0.33385 0.33480 +/- 0.00165 43/1 0.32752 0.33458 +/- 0.00162 44/1 0.34962 0.33502 +/- 0.00163 45/1 0.33518 0.33502 +/- 0.00158 46/1 0.33601 0.33505 +/- 0.00154 47/1 0.34462 0.33531 +/- 0.00152 48/1 0.33196 0.33522 +/- 0.00148 49/1 0.32787 0.33503 +/- 0.00145 50/1 0.33053 0.33492 +/- 0.00142 Creating state point statepoint.50.h5... =======================> TIMING STATISTICS <======================= Total time for initialization = 0.0000e+00 seconds Reading cross sections = 0.0000e+00 seconds Total time in simulation = 6.2339e-02 seconds Time in transport only = 4.2191e-02 seconds Time in inactive batches = 6.5212e-03 seconds Time in active batches = 5.5818e-02 seconds Time synchronizing fission bank = 2.9475e-03 seconds Sampling source sites = 2.6677e-03 seconds SEND/RECV source sites = 2.6321e-04 seconds Time accumulating tallies = 1.0428e-02 seconds Time writing statepoints = 6.1328e-03 seconds Total time for finalization = 7.4346e-05 seconds Total time elapsed = 6.5828e-02 seconds Calculation Rate (inactive) = 1.53346e+06 particles/second Calculation Rate (active) = 716620 particles/second ============================> RESULTS <============================ k-effective (Collision) = 0.33584 +/- 0.00213 k-effective (Track-length) = 0.33492 +/- 0.00142 k-effective (Absorption) = 0.33614 +/- 0.00455 Combined k-effective = 0.33514 +/- 0.00124 Leakage Fraction = 0.86230 +/- 0.00184 Creating state point openmc_simulation_n2.h5... Maximum neutron transport energy: 20000000 eV for I135 Initializing source particles... ====================> K EIGENVALUE SIMULATION <==================== Bat./Gen. k Average k ========= ======== ==================== 1/1 0.43652 2/1 0.36965 3/1 0.34291 4/1 0.33751 5/1 0.33269 6/1 0.33107 7/1 0.32994 8/1 0.33638 9/1 0.34974 10/1 0.34152 11/1 0.31659 12/1 0.34465 0.33062 +/- 0.01403 13/1 0.32762 0.32962 +/- 0.00816 14/1 0.32287 0.32794 +/- 0.00601 15/1 0.33523 0.32939 +/- 0.00488 16/1 0.34528 0.33204 +/- 0.00478 17/1 0.32589 0.33116 +/- 0.00414 18/1 0.34534 0.33294 +/- 0.00400 19/1 0.34441 0.33421 +/- 0.00375 20/1 0.32839 0.33363 +/- 0.00340 21/1 0.32874 0.33318 +/- 0.00311 22/1 0.33208 0.33309 +/- 0.00284 23/1 0.32915 0.33279 +/- 0.00263 24/1 0.33391 0.33287 +/- 0.00244 25/1 0.33268 0.33286 +/- 0.00227 26/1 0.33532 0.33301 +/- 0.00213 27/1 0.33315 0.33302 +/- 0.00200 28/1 0.33462 0.33311 +/- 0.00189 29/1 0.33976 0.33346 +/- 0.00182 30/1 0.32486 0.33303 +/- 0.00178 31/1 0.33359 0.33305 +/- 0.00169 32/1 0.34359 0.33353 +/- 0.00168 33/1 0.33078 0.33341 +/- 0.00161 34/1 0.32398 0.33302 +/- 0.00159 35/1 0.32786 0.33281 +/- 0.00154 36/1 0.33146 0.33276 +/- 0.00148 37/1 0.33186 0.33273 +/- 0.00143 38/1 0.33356 0.33276 +/- 0.00137 39/1 0.33102 0.33270 +/- 0.00133 40/1 0.33215 0.33268 +/- 0.00128 41/1 0.33335 0.33270 +/- 0.00124 42/1 0.34316 0.33303 +/- 0.00125 43/1 0.34486 0.33339 +/- 0.00126 44/1 0.33854 0.33354 +/- 0.00123 45/1 0.33576 0.33360 +/- 0.00120 46/1 0.32339 0.33332 +/- 0.00120 47/1 0.33626 0.33340 +/- 0.00117 48/1 0.34710 0.33376 +/- 0.00119 49/1 0.33917 0.33390 +/- 0.00117 50/1 0.33579 0.33394 +/- 0.00114 Creating state point statepoint.50.h5... =======================> TIMING STATISTICS <======================= Total time for initialization = 0.0000e+00 seconds Reading cross sections = 0.0000e+00 seconds Total time in simulation = 6.8805e-02 seconds Time in transport only = 4.7870e-02 seconds Time in inactive batches = 6.3043e-03 seconds Time in active batches = 6.2501e-02 seconds Time synchronizing fission bank = 2.7223e-03 seconds Sampling source sites = 2.4579e-03 seconds SEND/RECV source sites = 2.4881e-04 seconds Time accumulating tallies = 9.6293e-03 seconds Time writing statepoints = 6.1461e-03 seconds Total time for finalization = 6.4295e-05 seconds Total time elapsed = 7.2150e-02 seconds Calculation Rate (inactive) = 1.58623e+06 particles/second Calculation Rate (active) = 639989 particles/second ============================> RESULTS <============================ k-effective (Collision) = 0.33470 +/- 0.00236 k-effective (Track-length) = 0.33394 +/- 0.00114 k-effective (Absorption) = 0.33728 +/- 0.00486 Combined k-effective = 0.33432 +/- 0.00099 Leakage Fraction = 0.86203 +/- 0.00198 Creating state point openmc_simulation_n3.h5...
And finally let's look at the $^{135}$Xe density again:
results = openmc.deplete.ResultsList.from_hdf5('depletion_results.h5')
time, n_Xe135 = results.get_atoms('1', 'Xe135')
days = 24*60*60
plt.plot(time/days, n_Xe135)
plt.xlabel('Time [d]')
plt.ylabel('Xe135 [atoms]')
Text(0, 0.5, 'Xe135 [atoms]')