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Allow objects in addition to ids in Filters

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This commit is contained in:
Sterling Harper 2017-04-13 17:36:49 -04:00
parent bc4683be1c
commit 98ab232dc1
9 changed files with 686 additions and 548 deletions
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examples/jupyter/candu.ipynb
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examples/jupyter/pandas-dataframes.ipynb
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examples/jupyter/tally-arithmetic.ipynb
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@ -339,7 +339,7 @@
"outputs": [
{
"data": {
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"text/plain": [
"<IPython.core.display.Image object>"
]
@ -391,14 +391,14 @@
"\n",
"# Instantiate flux Tally in moderator and fuel\n",
"tally = openmc.Tally(name='flux')\n",
"tally.filters = [openmc.CellFilter([fuel_cell.id, moderator_cell.id])]\n",
"tally.filters = [openmc.CellFilter([fuel_cell, moderator_cell])]\n",
"tally.filters.append(energy_filter)\n",
"tally.scores = ['flux']\n",
"tallies_file.append(tally)\n",
"\n",
"# Instantiate reaction rate Tally in fuel\n",
"tally = openmc.Tally(name='fuel rxn rates')\n",
"tally.filters = [openmc.CellFilter([fuel_cell.id])]\n",
"tally.filters = [openmc.CellFilter(fuel_cell)]\n",
"tally.filters.append(energy_filter)\n",
"tally.scores = ['nu-fission', 'scatter']\n",
"tally.nuclides = [u238, u235]\n",
@ -406,7 +406,7 @@
"\n",
"# Instantiate reaction rate Tally in moderator\n",
"tally = openmc.Tally(name='moderator rxn rates')\n",
"tally.filters = [openmc.CellFilter([moderator_cell.id])]\n",
"tally.filters = [openmc.CellFilter(moderator_cell)]\n",
"tally.filters.append(energy_filter)\n",
"tally.scores = ['absorption', 'total']\n",
"tally.nuclides = [o16, h1]\n",
@ -480,7 +480,7 @@
"fuel_therm_abs_rate = openmc.Tally(name='fuel therm. abs. rate')\n",
"fuel_therm_abs_rate.scores = ['absorption']\n",
"fuel_therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625]),\n",
" openmc.CellFilter([fuel_cell.id])]\n",
" openmc.CellFilter([fuel_cell])]\n",
"tallies_file.append(fuel_therm_abs_rate)"
]
},
@ -512,7 +512,7 @@
"\n",
"# Instantiate flux Tally in moderator and fuel\n",
"tally = openmc.Tally(name='need-to-slice')\n",
"tally.filters = [openmc.CellFilter(bins=[fuel_cell.id, moderator_cell.id])]\n",
"tally.filters = [openmc.CellFilter([fuel_cell, moderator_cell])]\n",
"tally.filters.append(fine_energy_filter)\n",
"tally.scores = ['nu-fission', 'scatter']\n",
"tally.nuclides = [h1, u238]\n",
@ -576,35 +576,30 @@
" %%%%%%%%%%%\n",
"\n",
" | The OpenMC Monte Carlo Code\n",
" Copyright | 2011-2016 Massachusetts Institute of Technology\n",
" Copyright | 2011-2017 Massachusetts Institute of Technology\n",
" License | http://openmc.readthedocs.io/en/latest/license.html\n",
" Version | 0.8.0\n",
" Git SHA1 | da5563eddb5f2c2d6b2c9839d518de40962b78f2\n",
" Date/Time | 2016-10-31 12:54:36\n",
" OpenMP Threads | 4\n",
"\n",
" ===========================================================================\n",
" ========================> INITIALIZATION <=========================\n",
" ===========================================================================\n",
" Git SHA1 | bc4683be1c853fe6d0e31bccad416ef219e3efaf\n",
" Date/Time | 2017-04-13 17:26:05\n",
" MPI Processes | 1\n",
" OpenMP Threads | 1\n",
"\n",
" Reading settings XML file...\n",
" Reading geometry XML file...\n",
" Reading materials XML file...\n",
" Reading cross sections XML file...\n",
" Reading U235 from /home/romano/openmc/scripts/nndc_hdf5/U235.h5\n",
" Reading U238 from /home/romano/openmc/scripts/nndc_hdf5/U238.h5\n",
" Reading O16 from /home/romano/openmc/scripts/nndc_hdf5/O16.h5\n",
" Reading H1 from /home/romano/openmc/scripts/nndc_hdf5/H1.h5\n",
" Reading B10 from /home/romano/openmc/scripts/nndc_hdf5/B10.h5\n",
" Reading Zr90 from /home/romano/openmc/scripts/nndc_hdf5/Zr90.h5\n",
" Reading U235 from /home/smharper/openmc/data/nndc_hdf5/U235.h5\n",
" Reading U238 from /home/smharper/openmc/data/nndc_hdf5/U238.h5\n",
" Reading O16 from /home/smharper/openmc/data/nndc_hdf5/O16.h5\n",
" Reading H1 from /home/smharper/openmc/data/nndc_hdf5/H1.h5\n",
" Reading B10 from /home/smharper/openmc/data/nndc_hdf5/B10.h5\n",
" Reading Zr90 from /home/smharper/openmc/data/nndc_hdf5/Zr90.h5\n",
" Maximum neutron transport energy: 2.00000E+07 eV for U235\n",
" Reading tallies XML file...\n",
" Building neighboring cells lists for each surface...\n",
" Initializing source particles...\n",
"\n",
" ===========================================================================\n",
" ====================> K EIGENVALUE SIMULATION <====================\n",
" ===========================================================================\n",
"\n",
" Bat./Gen. k Average k \n",
" ========= ======== ==================== \n",
@ -617,48 +612,43 @@
" 7/1 0.99859 1.01409 +/- 0.01550\n",
" 8/1 1.03441 1.02086 +/- 0.01123\n",
" 9/1 1.06097 1.03089 +/- 0.01279\n",
" 10/1 1.06094 1.03690 +/- 0.01159\n",
" 11/1 1.04687 1.03856 +/- 0.00961\n",
" 12/1 1.02982 1.03731 +/- 0.00821\n",
" 13/1 1.03520 1.03705 +/- 0.00712\n",
" 14/1 0.99508 1.03239 +/- 0.00782\n",
" 15/1 1.03973 1.03312 +/- 0.00703\n",
" 16/1 1.03807 1.03357 +/- 0.00638\n",
" 17/1 1.03091 1.03335 +/- 0.00583\n",
" 18/1 1.01421 1.03188 +/- 0.00556\n",
" 19/1 0.99339 1.02913 +/- 0.00583\n",
" 20/1 1.04827 1.03040 +/- 0.00558\n",
" 10/1 1.06132 1.03698 +/- 0.01163\n",
" 11/1 1.04687 1.03863 +/- 0.00964\n",
" 12/1 1.02982 1.03737 +/- 0.00824\n",
" 13/1 1.03520 1.03710 +/- 0.00714\n",
" 14/1 0.99508 1.03243 +/- 0.00784\n",
" 15/1 1.03987 1.03317 +/- 0.00705\n",
" 16/1 1.02743 1.03265 +/- 0.00640\n",
" 17/1 1.02975 1.03241 +/- 0.00585\n",
" 18/1 0.99671 1.02966 +/- 0.00604\n",
" 19/1 1.02040 1.02900 +/- 0.00563\n",
" 20/1 1.02024 1.02842 +/- 0.00527\n",
" Creating state point statepoint.20.h5...\n",
"\n",
" ===========================================================================\n",
" ======================> SIMULATION FINISHED <======================\n",
" ===========================================================================\n",
"\n",
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 5.0418E-01 seconds\n",
" Reading cross sections = 3.6765E-01 seconds\n",
" Total time in simulation = 8.8388E+00 seconds\n",
" Time in transport only = 8.7431E+00 seconds\n",
" Time in inactive batches = 1.4676E+00 seconds\n",
" Time in active batches = 7.3713E+00 seconds\n",
" Time synchronizing fission bank = 2.2671E-03 seconds\n",
" Sampling source sites = 1.6677E-03 seconds\n",
" SEND/RECV source sites = 5.5964E-04 seconds\n",
" Time accumulating tallies = 9.0487E-05 seconds\n",
" Total time for finalization = 2.7160E-03 seconds\n",
" Total time elapsed = 9.3633E+00 seconds\n",
" Calculation Rate (inactive) = 8517.40 neutrons/second\n",
" Calculation Rate (active) = 5087.33 neutrons/second\n",
" Total time for initialization = 2.2576E-01 seconds\n",
" Reading cross sections = 1.8005E-01 seconds\n",
" Total time in simulation = 9.6105E+00 seconds\n",
" Time in transport only = 9.5952E+00 seconds\n",
" Time in inactive batches = 1.4678E+00 seconds\n",
" Time in active batches = 8.1427E+00 seconds\n",
" Time synchronizing fission bank = 2.6325E-03 seconds\n",
" Sampling source sites = 1.5038E-03 seconds\n",
" SEND/RECV source sites = 8.8069E-04 seconds\n",
" Time accumulating tallies = 2.0568E-04 seconds\n",
" Total time for finalization = 1.5435E-03 seconds\n",
" Total time elapsed = 9.8506E+00 seconds\n",
" Calculation Rate (inactive) = 8516.30 neutrons/second\n",
" Calculation Rate (active) = 4605.35 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
" k-effective (Collision) = 1.02791 +/- 0.00553\n",
" k-effective (Track-length) = 1.03040 +/- 0.00558\n",
" k-effective (Absorption) = 1.02011 +/- 0.00491\n",
" Combined k-effective = 1.02461 +/- 0.00398\n",
" Leakage Fraction = 0.01677 +/- 0.00109\n",
" k-effective (Collision) = 1.02889 +/- 0.00492\n",
" k-effective (Track-length) = 1.02842 +/- 0.00527\n",
" k-effective (Absorption) = 1.02637 +/- 0.00349\n",
" Combined k-effective = 1.02700 +/- 0.00291\n",
" Leakage Fraction = 0.01717 +/- 0.00107\n",
"\n"
]
},
@ -743,8 +733,8 @@
" <th>0</th>\n",
" <td>total</td>\n",
" <td>(nu-fission / (absorption + current))</td>\n",
" <td>1.02431</td>\n",
" <td>0.00704</td>\n",
" <td>1.023002</td>\n",
" <td>0.006647</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -752,7 +742,7 @@
],
"text/plain": [
" nuclide score mean std. dev.\n",
"0 total (nu-fission / (absorption + current)) 1.02e+00 7.04e-03"
"0 total (nu-fission / (absorption + current)) 1.02e+00 6.65e-03"
]
},
"execution_count": 24,
@ -814,8 +804,8 @@
" <td>0.625</td>\n",
" <td>total</td>\n",
" <td>(absorption + current)</td>\n",
" <td>0.695303</td>\n",
" <td>0.005091</td>\n",
" <td>0.694368</td>\n",
" <td>0.004606</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -823,10 +813,10 @@
],
"text/plain": [
" energy low [eV] energy high [eV] nuclide score mean \\\n",
"0 0.00e+00 6.25e-01 total (absorption + current) 6.95e-01 \n",
"0 0.00e+00 6.25e-01 total (absorption + current) 6.94e-01 \n",
"\n",
" std. dev. \n",
"0 5.09e-03 "
"0 4.61e-03 "
]
},
"execution_count": 25,
@ -882,8 +872,8 @@
" <td>0.625</td>\n",
" <td>total</td>\n",
" <td>nu-fission</td>\n",
" <td>1.202639</td>\n",
" <td>0.010348</td>\n",
" <td>1.203099</td>\n",
" <td>0.009615</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -891,7 +881,7 @@
],
"text/plain": [
" energy low [eV] energy high [eV] nuclide score mean std. dev.\n",
"0 0.00e+00 6.25e-01 total nu-fission 1.20e+00 1.03e-02"
"0 0.00e+00 6.25e-01 total nu-fission 1.20e+00 9.61e-03"
]
},
"execution_count": 26,
@ -947,8 +937,8 @@
" <td>10000</td>\n",
" <td>total</td>\n",
" <td>absorption</td>\n",
" <td>0.749349</td>\n",
" <td>0.006731</td>\n",
" <td>0.749423</td>\n",
" <td>0.006089</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -959,7 +949,7 @@
"0 0.00e+00 6.25e-01 10000 total absorption 7.49e-01 \n",
"\n",
" std. dev. \n",
"0 6.73e-03 "
"0 6.09e-03 "
]
},
"execution_count": 27,
@ -1013,8 +1003,8 @@
" <td>10000</td>\n",
" <td>total</td>\n",
" <td>(nu-fission / absorption)</td>\n",
" <td>1.663736</td>\n",
" <td>0.015707</td>\n",
" <td>1.663727</td>\n",
" <td>0.014403</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1025,7 +1015,7 @@
"0 0.00e+00 6.25e-01 10000 total \n",
"\n",
" score mean std. dev. \n",
"0 (nu-fission / absorption) 1.66e+00 1.57e-02 "
"0 (nu-fission / absorption) 1.66e+00 1.44e-02 "
]
},
"execution_count": 28,
@ -1076,8 +1066,8 @@
" <td>0.625</td>\n",
" <td>total</td>\n",
" <td>(absorption + current)</td>\n",
" <td>0.985102</td>\n",
" <td>0.005855</td>\n",
" <td>0.984668</td>\n",
" <td>0.005509</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1088,7 +1078,7 @@
"0 0.00e+00 6.25e-01 total (absorption + current) 9.85e-01 \n",
"\n",
" std. dev. \n",
"0 5.86e-03 "
"0 5.51e-03 "
]
},
"execution_count": 29,
@ -1138,8 +1128,8 @@
" <td>0.625</td>\n",
" <td>total</td>\n",
" <td>(absorption / (absorption + current))</td>\n",
" <td>0.997407</td>\n",
" <td>0.008492</td>\n",
" <td>0.997439</td>\n",
" <td>0.007548</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1150,7 +1140,7 @@
"0 0.00e+00 6.25e-01 total \n",
"\n",
" score mean std. dev. \n",
"0 (absorption / (absorption + current)) 9.97e-01 8.49e-03 "
"0 (absorption / (absorption + current)) 9.97e-01 7.55e-03 "
]
},
"execution_count": 30,
@ -1202,8 +1192,8 @@
" <td>10000</td>\n",
" <td>total</td>\n",
" <td>((((((absorption + current) * nu-fission) * ab...</td>\n",
" <td>1.02431</td>\n",
" <td>0.02062</td>\n",
" <td>1.023002</td>\n",
" <td>0.018791</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1214,7 +1204,7 @@
"0 0.00e+00 6.25e-01 10000 total \n",
"\n",
" score mean std. dev. \n",
"0 ((((((absorption + current) * nu-fission) * ab... 1.02e+00 2.06e-02 "
"0 ((((((absorption + current) * nu-fission) * ab... 1.02e+00 1.88e-02 "
]
},
"execution_count": 31,
@ -1284,8 +1274,8 @@
" <td>6.250000e-01</td>\n",
" <td>(U238 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>6.662479e-07</td>\n",
" <td>6.039323e-09</td>\n",
" <td>6.659486e-07</td>\n",
" <td>5.627975e-09</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
@ -1294,8 +1284,8 @@
" <td>6.250000e-01</td>\n",
" <td>(U238 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>2.099897e-01</td>\n",
" <td>1.843251e-03</td>\n",
" <td>2.099901e-01</td>\n",
" <td>1.748379e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
@ -1304,8 +1294,8 @@
" <td>6.250000e-01</td>\n",
" <td>(U235 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>3.568130e-01</td>\n",
" <td>3.255144e-03</td>\n",
" <td>3.566329e-01</td>\n",
" <td>3.030782e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
@ -1314,8 +1304,8 @@
" <td>6.250000e-01</td>\n",
" <td>(U235 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>5.555326e-03</td>\n",
" <td>4.893022e-05</td>\n",
" <td>5.555466e-03</td>\n",
" <td>4.635318e-05</td>\n",
" </tr>\n",
" <tr>\n",
" <th>4</th>\n",
@ -1324,8 +1314,8 @@
" <td>2.000000e+07</td>\n",
" <td>(U238 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>7.215044e-03</td>\n",
" <td>4.968448e-05</td>\n",
" <td>7.251304e-03</td>\n",
" <td>5.161998e-05</td>\n",
" </tr>\n",
" <tr>\n",
" <th>5</th>\n",
@ -1334,8 +1324,8 @@
" <td>2.000000e+07</td>\n",
" <td>(U238 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>2.273966e-01</td>\n",
" <td>8.969811e-04</td>\n",
" <td>2.272661e-01</td>\n",
" <td>9.576939e-04</td>\n",
" </tr>\n",
" <tr>\n",
" <th>6</th>\n",
@ -1344,8 +1334,8 @@
" <td>2.000000e+07</td>\n",
" <td>(U235 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>7.969615e-03</td>\n",
" <td>5.374119e-05</td>\n",
" <td>7.920169e-03</td>\n",
" <td>5.751231e-05</td>\n",
" </tr>\n",
" <tr>\n",
" <th>7</th>\n",
@ -1354,8 +1344,8 @@
" <td>2.000000e+07</td>\n",
" <td>(U235 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>3.362798e-03</td>\n",
" <td>1.286767e-05</td>\n",
" <td>3.358280e-03</td>\n",
" <td>1.341281e-05</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1373,14 +1363,14 @@
"7 10000 6.25e-01 2.00e+07 (U235 / total) \n",
"\n",
" score mean std. dev. \n",
"0 (nu-fission / flux) 6.66e-07 6.04e-09 \n",
"1 (scatter / flux) 2.10e-01 1.84e-03 \n",
"2 (nu-fission / flux) 3.57e-01 3.26e-03 \n",
"3 (scatter / flux) 5.56e-03 4.89e-05 \n",
"4 (nu-fission / flux) 7.22e-03 4.97e-05 \n",
"5 (scatter / flux) 2.27e-01 8.97e-04 \n",
"6 (nu-fission / flux) 7.97e-03 5.37e-05 \n",
"7 (scatter / flux) 3.36e-03 1.29e-05 "
"0 (nu-fission / flux) 6.66e-07 5.63e-09 \n",
"1 (scatter / flux) 2.10e-01 1.75e-03 \n",
"2 (nu-fission / flux) 3.57e-01 3.03e-03 \n",
"3 (scatter / flux) 5.56e-03 4.64e-05 \n",
"4 (nu-fission / flux) 7.25e-03 5.16e-05 \n",
"5 (scatter / flux) 2.27e-01 9.58e-04 \n",
"6 (nu-fission / flux) 7.92e-03 5.75e-05 \n",
"7 (scatter / flux) 3.36e-03 1.34e-05 "
]
},
"execution_count": 33,
@ -1411,11 +1401,11 @@
"name": "stdout",
"output_type": "stream",
"text": [
"[[[ 6.66247898e-07]\n",
" [ 3.56812954e-01]]\n",
"[[[ 6.65948580e-07]\n",
" [ 3.56632881e-01]]\n",
"\n",
" [[ 7.21504433e-03]\n",
" [ 7.96961502e-03]]]\n"
" [[ 7.25130446e-03]\n",
" [ 7.92016892e-03]]]\n"
]
}
],
@ -1443,9 +1433,9 @@
"name": "stdout",
"output_type": "stream",
"text": [
"[[[ 0.00555533]]\n",
"[[[ 0.00555547]]\n",
"\n",
" [[ 0.0033628 ]]]\n"
" [[ 0.00335828]]]\n"
]
}
],
@ -1467,8 +1457,8 @@
"name": "stdout",
"output_type": "stream",
"text": [
"[[[ 0.22739657]\n",
" [ 0.0033628 ]]]\n"
"[[[ 0.22726611]\n",
" [ 0.00335828]]]\n"
]
}
],
@ -1520,7 +1510,7 @@
" <td>U238</td>\n",
" <td>nu-fission</td>\n",
" <td>0.000002</td>\n",
" <td>1.057199e-08</td>\n",
" <td>9.679304e-09</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
@ -1529,8 +1519,8 @@
" <td>6.250000e-01</td>\n",
" <td>U235</td>\n",
" <td>nu-fission</td>\n",
" <td>0.856784</td>\n",
" <td>5.730044e-03</td>\n",
" <td>0.854805</td>\n",
" <td>5.239673e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
@ -1539,8 +1529,8 @@
" <td>2.000000e+07</td>\n",
" <td>U238</td>\n",
" <td>nu-fission</td>\n",
" <td>0.082495</td>\n",
" <td>5.176027e-04</td>\n",
" <td>0.082978</td>\n",
" <td>5.346135e-04</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
@ -1549,8 +1539,8 @@
" <td>2.000000e+07</td>\n",
" <td>U235</td>\n",
" <td>nu-fission</td>\n",
" <td>0.091123</td>\n",
" <td>5.574052e-04</td>\n",
" <td>0.090632</td>\n",
" <td>5.981942e-04</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1559,15 +1549,15 @@
"text/plain": [
" cell energy low [eV] energy high [eV] nuclide score mean \\\n",
"0 10000 0.00e+00 6.25e-01 U238 nu-fission 1.60e-06 \n",
"1 10000 0.00e+00 6.25e-01 U235 nu-fission 8.57e-01 \n",
"2 10000 6.25e-01 2.00e+07 U238 nu-fission 8.25e-02 \n",
"3 10000 6.25e-01 2.00e+07 U235 nu-fission 9.11e-02 \n",
"1 10000 0.00e+00 6.25e-01 U235 nu-fission 8.55e-01 \n",
"2 10000 6.25e-01 2.00e+07 U238 nu-fission 8.30e-02 \n",
"3 10000 6.25e-01 2.00e+07 U235 nu-fission 9.06e-02 \n",
"\n",
" std. dev. \n",
"0 1.06e-08 \n",
"1 5.73e-03 \n",
"2 5.18e-04 \n",
"3 5.57e-04 "
"0 9.68e-09 \n",
"1 5.24e-03 \n",
"2 5.35e-04 \n",
"3 5.98e-04 "
]
},
"execution_count": 37,
@ -1613,8 +1603,8 @@
" <td>1.080060e-01</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>4.547947</td>\n",
" <td>0.028000</td>\n",
" <td>4.541188</td>\n",
" <td>0.025230</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
@ -1623,8 +1613,8 @@
" <td>1.166529e+00</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.003068</td>\n",
" <td>0.008587</td>\n",
" <td>2.001332</td>\n",
" <td>0.006754</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
@ -1633,8 +1623,8 @@
" <td>1.259921e+01</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>1.647225</td>\n",
" <td>0.011136</td>\n",
" <td>1.639292</td>\n",
" <td>0.011374</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
@ -1643,8 +1633,8 @@
" <td>1.360790e+02</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>1.831367</td>\n",
" <td>0.010196</td>\n",
" <td>1.821633</td>\n",
" <td>0.009590</td>\n",
" </tr>\n",
" <tr>\n",
" <th>4</th>\n",
@ -1653,8 +1643,8 @@
" <td>1.469734e+03</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.039613</td>\n",
" <td>0.008059</td>\n",
" <td>2.032395</td>\n",
" <td>0.009953</td>\n",
" </tr>\n",
" <tr>\n",
" <th>5</th>\n",
@ -1663,8 +1653,8 @@
" <td>1.587401e+04</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.137523</td>\n",
" <td>0.012885</td>\n",
" <td>2.120745</td>\n",
" <td>0.011090</td>\n",
" </tr>\n",
" <tr>\n",
" <th>6</th>\n",
@ -1673,8 +1663,8 @@
" <td>1.714488e+05</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.170725</td>\n",
" <td>0.012669</td>\n",
" <td>2.181709</td>\n",
" <td>0.013602</td>\n",
" </tr>\n",
" <tr>\n",
" <th>7</th>\n",
@ -1683,8 +1673,8 @@
" <td>1.851749e+06</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.002724</td>\n",
" <td>0.010768</td>\n",
" <td>2.013644</td>\n",
" <td>0.009219</td>\n",
" </tr>\n",
" <tr>\n",
" <th>8</th>\n",
@ -1693,8 +1683,8 @@
" <td>2.000000e+07</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>0.371624</td>\n",
" <td>0.002959</td>\n",
" <td>0.372640</td>\n",
" <td>0.002903</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1702,26 +1692,26 @@
],
"text/plain": [
" cell energy low [eV] energy high [eV] nuclide score mean \\\n",
"0 10002 1.00e-02 1.08e-01 H1 scatter 4.55e+00 \n",
"0 10002 1.00e-02 1.08e-01 H1 scatter 4.54e+00 \n",
"1 10002 1.08e-01 1.17e+00 H1 scatter 2.00e+00 \n",
"2 10002 1.17e+00 1.26e+01 H1 scatter 1.65e+00 \n",
"3 10002 1.26e+01 1.36e+02 H1 scatter 1.83e+00 \n",
"4 10002 1.36e+02 1.47e+03 H1 scatter 2.04e+00 \n",
"5 10002 1.47e+03 1.59e+04 H1 scatter 2.14e+00 \n",
"6 10002 1.59e+04 1.71e+05 H1 scatter 2.17e+00 \n",
"7 10002 1.71e+05 1.85e+06 H1 scatter 2.00e+00 \n",
"8 10002 1.85e+06 2.00e+07 H1 scatter 3.72e-01 \n",
"2 10002 1.17e+00 1.26e+01 H1 scatter 1.64e+00 \n",
"3 10002 1.26e+01 1.36e+02 H1 scatter 1.82e+00 \n",
"4 10002 1.36e+02 1.47e+03 H1 scatter 2.03e+00 \n",
"5 10002 1.47e+03 1.59e+04 H1 scatter 2.12e+00 \n",
"6 10002 1.59e+04 1.71e+05 H1 scatter 2.18e+00 \n",
"7 10002 1.71e+05 1.85e+06 H1 scatter 2.01e+00 \n",
"8 10002 1.85e+06 2.00e+07 H1 scatter 3.73e-01 \n",
"\n",
" std. dev. \n",
"0 2.80e-02 \n",
"1 8.59e-03 \n",
"2 1.11e-02 \n",
"3 1.02e-02 \n",
"4 8.06e-03 \n",
"5 1.29e-02 \n",
"6 1.27e-02 \n",
"7 1.08e-02 \n",
"8 2.96e-03 "
"0 2.52e-02 \n",
"1 6.75e-03 \n",
"2 1.14e-02 \n",
"3 9.59e-03 \n",
"4 9.95e-03 \n",
"5 1.11e-02 \n",
"6 1.36e-02 \n",
"7 9.22e-03 \n",
"8 2.90e-03 "
]
},
"execution_count": 38,

2
examples/python/basic/build-xml.py
View file

@ -95,7 +95,7 @@ settings_file.export_to_xml()
###############################################################################
# Instantiate some tally Filters
cell_filter = openmc.CellFilter(100)
cell_filter = openmc.CellFilter(cell2)
energy_filter = openmc.EnergyFilter([0., 20.e6])
energyout_filter = openmc.EnergyoutFilter([0., 20.e6])

2
examples/python/lattice/hexagonal/build-xml.py
View file

@ -153,7 +153,7 @@ plot_file.export_to_xml()
# Instantiate a distribcell Tally
tally = openmc.Tally(tally_id=1)
tally.filters = [openmc.DistribcellFilter(cell2.id)]
tally.filters = [openmc.DistribcellFilter(cell2)]
tally.scores = ['total']
# Instantiate a Tallies collection and export to XML