Merge remote-tracking branch 'upstream/develop' into mg

This commit is contained in:
Adam Nelson 2016-02-14 15:35:56 -05:00
commit e68bed1ad7
11 changed files with 1436 additions and 1174 deletions

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@ -518,8 +518,9 @@
" Copyright: 2011-2015 Massachusetts Institute of Technology\n",
" License: http://mit-crpg.github.io/openmc/license.html\n",
" Version: 0.7.1\n",
" Git SHA1: ea9fb637f63f9374c7436456141afa850b84acf9\n",
" Date/Time: 2016-01-14 07:16:05\n",
" Git SHA1: 34381b40a9445a727e360873aaa6ef892af1cb6a\n",
" Date/Time: 2016-02-07 15:58:16\n",
" MPI Processes: 1\n",
"\n",
" ===========================================================================\n",
" ========================> INITIALIZATION <=========================\n",
@ -604,20 +605,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 1.1720E+00 seconds\n",
" Reading cross sections = 9.0300E-01 seconds\n",
" Total time in simulation = 1.7319E+01 seconds\n",
" Time in transport only = 1.7310E+01 seconds\n",
" Time in inactive batches = 1.9120E+00 seconds\n",
" Time in active batches = 1.5407E+01 seconds\n",
" Time synchronizing fission bank = 2.0000E-03 seconds\n",
" Sampling source sites = 2.0000E-03 seconds\n",
" SEND/RECV source sites = 0.0000E+00 seconds\n",
" Total time for initialization = 3.2100E-01 seconds\n",
" Reading cross sections = 7.4000E-02 seconds\n",
" Total time in simulation = 8.3830E+00 seconds\n",
" Time in transport only = 8.3670E+00 seconds\n",
" Time in inactive batches = 1.0330E+00 seconds\n",
" Time in active batches = 7.3500E+00 seconds\n",
" Time synchronizing fission bank = 4.0000E-03 seconds\n",
" Sampling source sites = 1.0000E-03 seconds\n",
" SEND/RECV source sites = 3.0000E-03 seconds\n",
" Time accumulating tallies = 0.0000E+00 seconds\n",
" Total time for finalization = 1.0000E-03 seconds\n",
" Total time elapsed = 1.8507E+01 seconds\n",
" Calculation Rate (inactive) = 13075.3 neutrons/second\n",
" Calculation Rate (active) = 6490.56 neutrons/second\n",
" Total time elapsed = 8.7140E+00 seconds\n",
" Calculation Rate (inactive) = 24201.4 neutrons/second\n",
" Calculation Rate (active) = 13605.4 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
@ -794,19 +795,19 @@
" <tbody>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>1</td>\n",
" <td>1</td>\n",
" <td>total</td>\n",
" <td>0.668323</td>\n",
" <td>0.001264</td>\n",
" <td> 1</td>\n",
" <td> 1</td>\n",
" <td> total</td>\n",
" <td> 0.668323</td>\n",
" <td> 0.001264</td>\n",
" </tr>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>1</td>\n",
" <td>2</td>\n",
" <td>total</td>\n",
" <td>1.293258</td>\n",
" <td>0.007624</td>\n",
" <td> 1</td>\n",
" <td> 2</td>\n",
" <td> total</td>\n",
" <td> 1.293258</td>\n",
" <td> 0.007624</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -896,7 +897,8 @@
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
@ -906,34 +908,36 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>1</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>total</td>\n",
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td>4.884981e-15</td>\n",
" <td>0.011274</td>\n",
" <td> 1</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> total</td>\n",
" <td> (((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td> 4.884981e-15</td>\n",
" <td> 0.011274</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>1</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>total</td>\n",
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td>1.221245e-15</td>\n",
" <td>0.001802</td>\n",
" <td> 1</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> total</td>\n",
" <td> (((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td> 1.221245e-15</td>\n",
" <td> 0.001802</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide \\\n",
"0 1 (0.0e+00 - 6.3e-07) total \n",
"1 1 (6.3e-07 - 2.0e+01) total \n",
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
"0 1 0.00e+00 6.25e-07 total \n",
"1 1 6.25e-07 2.00e+01 total \n",
"\n",
" score mean std. dev. \n",
"0 (((total / flux) - (absorption / flux)) - (sca... 4.884981e-15 0.011274 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... 1.221245e-15 0.001802 "
" score mean std. dev. \n",
"0 (((total / flux) - (absorption / flux)) - (sca... 4.88e-15 1.13e-02 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... 1.22e-15 1.80e-03 "
]
},
"execution_count": 23,
@ -972,7 +976,8 @@
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
@ -982,34 +987,36 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>1</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>total</td>\n",
" <td>((absorption / flux) / (total / flux))</td>\n",
" <td>0.076219</td>\n",
" <td>0.000651</td>\n",
" <td> 1</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> total</td>\n",
" <td> ((absorption / flux) / (total / flux))</td>\n",
" <td> 0.076219</td>\n",
" <td> 0.000651</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>1</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>total</td>\n",
" <td>((absorption / flux) / (total / flux))</td>\n",
" <td>0.019319</td>\n",
" <td>0.000086</td>\n",
" <td> 1</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> total</td>\n",
" <td> ((absorption / flux) / (total / flux))</td>\n",
" <td> 0.019319</td>\n",
" <td> 0.000086</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide score \\\n",
"0 1 (0.0e+00 - 6.3e-07) total ((absorption / flux) / (total / flux)) \n",
"1 1 (6.3e-07 - 2.0e+01) total ((absorption / flux) / (total / flux)) \n",
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
"0 1 0.00e+00 6.25e-07 total \n",
"1 1 6.25e-07 2.00e+01 total \n",
"\n",
" mean std. dev. \n",
"0 0.076219 0.000651 \n",
"1 0.019319 0.000086 "
" score mean std. dev. \n",
"0 ((absorption / flux) / (total / flux)) 7.62e-02 6.51e-04 \n",
"1 ((absorption / flux) / (total / flux)) 1.93e-02 8.65e-05 "
]
},
"execution_count": 24,
@ -1041,7 +1048,8 @@
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
@ -1051,34 +1059,36 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>1</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>total</td>\n",
" <td>((scatter / flux) / (total / flux))</td>\n",
" <td>0.923781</td>\n",
" <td>0.007714</td>\n",
" <td> 1</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> total</td>\n",
" <td> ((scatter / flux) / (total / flux))</td>\n",
" <td> 0.923781</td>\n",
" <td> 0.007714</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>1</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>total</td>\n",
" <td>((scatter / flux) / (total / flux))</td>\n",
" <td>0.980681</td>\n",
" <td>0.002617</td>\n",
" <td> 1</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> total</td>\n",
" <td> ((scatter / flux) / (total / flux))</td>\n",
" <td> 0.980681</td>\n",
" <td> 0.002617</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide score \\\n",
"0 1 (0.0e+00 - 6.3e-07) total ((scatter / flux) / (total / flux)) \n",
"1 1 (6.3e-07 - 2.0e+01) total ((scatter / flux) / (total / flux)) \n",
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
"0 1 0.00e+00 6.25e-07 total \n",
"1 1 6.25e-07 2.00e+01 total \n",
"\n",
" mean std. dev. \n",
"0 0.923781 0.007714 \n",
"1 0.980681 0.002617 "
" score mean std. dev. \n",
"0 ((scatter / flux) / (total / flux)) 9.24e-01 7.71e-03 \n",
"1 ((scatter / flux) / (total / flux)) 9.81e-01 2.62e-03 "
]
},
"execution_count": 25,
@ -1117,7 +1127,8 @@
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
@ -1127,34 +1138,36 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>1</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>total</td>\n",
" <td>(((absorption / flux) / (total / flux)) + ((sc...</td>\n",
" <td>1</td>\n",
" <td>0.007741</td>\n",
" <td> 1</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> total</td>\n",
" <td> (((absorption / flux) / (total / flux)) + ((sc...</td>\n",
" <td> 1</td>\n",
" <td> 0.007741</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>1</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>total</td>\n",
" <td>(((absorption / flux) / (total / flux)) + ((sc...</td>\n",
" <td>1</td>\n",
" <td>0.002619</td>\n",
" <td> 1</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> total</td>\n",
" <td> (((absorption / flux) / (total / flux)) + ((sc...</td>\n",
" <td> 1</td>\n",
" <td> 0.002619</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide \\\n",
"0 1 (0.0e+00 - 6.3e-07) total \n",
"1 1 (6.3e-07 - 2.0e+01) total \n",
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
"0 1 0.00e+00 6.25e-07 total \n",
"1 1 6.25e-07 2.00e+01 total \n",
"\n",
" score mean std. dev. \n",
"0 (((absorption / flux) / (total / flux)) + ((sc... 1 0.007741 \n",
"1 (((absorption / flux) / (total / flux)) + ((sc... 1 0.002619 "
" score mean std. dev. \n",
"0 (((absorption / flux) / (total / flux)) + ((sc... 1.00e+00 7.74e-03 \n",
"1 (((absorption / flux) / (total / flux)) + ((sc... 1.00e+00 2.62e-03 "
]
},
"execution_count": 26,

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@ -366,7 +366,7 @@
"outputs": [
{
"data": {
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"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\nVE6KjgAAAABJRU5ErkJggg==\n",
"text/plain": [
"<IPython.core.display.Image object>"
]
@ -472,7 +472,7 @@
"# Resonance Escape Probability tallies\n",
"therm_abs_rate = openmc.Tally(name='therm. abs. rate')\n",
"therm_abs_rate.add_score('absorption')\n",
"therm_abs_rate.add_filter(openmc.Filter(type='energy', bins=[0., 0.625]))\n",
"therm_abs_rate.add_filter(openmc.Filter(type='energy', bins=[0., 0.625e-6]))\n",
"tallies_file.add_tally(therm_abs_rate)"
]
},
@ -487,7 +487,7 @@
"# Thermal Flux Utilization tallies\n",
"fuel_therm_abs_rate = openmc.Tally(name='fuel therm. abs. rate')\n",
"fuel_therm_abs_rate.add_score('absorption')\n",
"fuel_therm_abs_rate.add_filter(openmc.Filter(type='energy', bins=[0., 0.625]))\n",
"fuel_therm_abs_rate.add_filter(openmc.Filter(type='energy', bins=[0., 0.625e-6]))\n",
"fuel_therm_abs_rate.add_filter(openmc.Filter(type='cell', bins=[fuel_cell.id]))\n",
"tallies_file.add_tally(fuel_therm_abs_rate)"
]
@ -503,7 +503,7 @@
"# Fast Fission Factor tallies\n",
"therm_fiss_rate = openmc.Tally(name='therm. fiss. rate')\n",
"therm_fiss_rate.add_score('nu-fission')\n",
"therm_fiss_rate.add_filter(openmc.Filter(type='energy', bins=[0., 0.625]))\n",
"therm_fiss_rate.add_filter(openmc.Filter(type='energy', bins=[0., 0.625e-6]))\n",
"tallies_file.add_tally(therm_fiss_rate)"
]
},
@ -576,8 +576,9 @@
" Copyright: 2011-2015 Massachusetts Institute of Technology\n",
" License: http://mit-crpg.github.io/openmc/license.html\n",
" Version: 0.7.1\n",
" Git SHA1: ea9fb637f63f9374c7436456141afa850b84acf9\n",
" Date/Time: 2016-01-14 07:00:14\n",
" Git SHA1: 34381b40a9445a727e360873aaa6ef892af1cb6a\n",
" Date/Time: 2016-02-07 16:05:17\n",
" MPI Processes: 1\n",
"\n",
" ===========================================================================\n",
" ========================> INITIALIZATION <=========================\n",
@ -633,20 +634,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 1.2510E+00 seconds\n",
" Reading cross sections = 9.7600E-01 seconds\n",
" Total time in simulation = 1.5844E+01 seconds\n",
" Time in transport only = 1.5834E+01 seconds\n",
" Time in inactive batches = 2.2840E+00 seconds\n",
" Time in active batches = 1.3560E+01 seconds\n",
" Time synchronizing fission bank = 3.0000E-03 seconds\n",
" Sampling source sites = 2.0000E-03 seconds\n",
" SEND/RECV source sites = 1.0000E-03 seconds\n",
" Total time for initialization = 3.4700E-01 seconds\n",
" Reading cross sections = 9.1000E-02 seconds\n",
" Total time in simulation = 7.3920E+00 seconds\n",
" Time in transport only = 7.3820E+00 seconds\n",
" Time in inactive batches = 1.0930E+00 seconds\n",
" Time in active batches = 6.2990E+00 seconds\n",
" Time synchronizing fission bank = 2.0000E-03 seconds\n",
" Sampling source sites = 1.0000E-03 seconds\n",
" SEND/RECV source sites = 0.0000E+00 seconds\n",
" Time accumulating tallies = 0.0000E+00 seconds\n",
" Total time for finalization = 1.0000E-03 seconds\n",
" Total time elapsed = 1.7110E+01 seconds\n",
" Calculation Rate (inactive) = 5472.85 neutrons/second\n",
" Calculation Rate (active) = 2765.49 neutrons/second\n",
" Total time for finalization = 2.0000E-03 seconds\n",
" Total time elapsed = 7.7510E+00 seconds\n",
" Calculation Rate (inactive) = 11436.4 neutrons/second\n",
" Calculation Rate (active) = 5953.33 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
@ -758,18 +759,18 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>total</td>\n",
" <td>(nu-fission / absorption)</td>\n",
" <td>1.040166</td>\n",
" <td>0.009069</td>\n",
" <td> total</td>\n",
" <td> (nu-fission / absorption)</td>\n",
" <td> 1.040166</td>\n",
" <td> 0.009069</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" nuclide score mean std. dev.\n",
"0 total (nu-fission / absorption) 1.040166 0.009069"
" nuclide score mean std. dev.\n",
"0 total (nu-fission / absorption) 1.04e+00 9.07e-03"
]
},
"execution_count": 26,
@ -809,7 +810,8 @@
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
@ -819,19 +821,20 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>(0.0e+00 - 6.2e-01)</td>\n",
" <td>total</td>\n",
" <td>absorption</td>\n",
" <td>0.95938</td>\n",
" <td>0.008187</td>\n",
" <td> 0</td>\n",
" <td> 0.000001</td>\n",
" <td> total</td>\n",
" <td> absorption</td>\n",
" <td> 0.694707</td>\n",
" <td> 0.006699</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" energy [MeV] nuclide score mean std. dev.\n",
"0 (0.0e+00 - 6.2e-01) total absorption 0.95938 0.008187"
" energy low [MeV] energy high [MeV] nuclide score mean std. dev.\n",
"0 0.00e+00 6.25e-07 total absorption 6.95e-01 6.70e-03"
]
},
"execution_count": 27,
@ -869,7 +872,8 @@
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
@ -879,19 +883,20 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>(0.0e+00 - 6.2e-01)</td>\n",
" <td>total</td>\n",
" <td>nu-fission</td>\n",
" <td>1.090899</td>\n",
" <td>0.010602</td>\n",
" <td> 0</td>\n",
" <td> 0.000001</td>\n",
" <td> total</td>\n",
" <td> nu-fission</td>\n",
" <td> 1.201216</td>\n",
" <td> 0.012288</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" energy [MeV] nuclide score mean std. dev.\n",
"0 (0.0e+00 - 6.2e-01) total nu-fission 1.090899 0.010602"
" energy low [MeV] energy high [MeV] nuclide score mean std. dev.\n",
"0 0.00e+00 6.25e-07 total nu-fission 1.20e+00 1.23e-02"
]
},
"execution_count": 28,
@ -930,7 +935,8 @@
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>cell</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
@ -941,20 +947,24 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>(0.0e+00 - 6.2e-01)</td>\n",
" <td>10000</td>\n",
" <td>total</td>\n",
" <td>absorption</td>\n",
" <td>0.803413</td>\n",
" <td>0.007031</td>\n",
" <td> 0</td>\n",
" <td> 0.000001</td>\n",
" <td> 10000</td>\n",
" <td> total</td>\n",
" <td> absorption</td>\n",
" <td> 0.74925</td>\n",
" <td> 0.008257</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" energy [MeV] cell nuclide score mean std. dev.\n",
"0 (0.0e+00 - 6.2e-01) 10000 total absorption 0.803413 0.007031"
" energy low [MeV] energy high [MeV] cell nuclide score mean \\\n",
"0 0.00e+00 6.25e-07 10000 total absorption 7.49e-01 \n",
"\n",
" std. dev. \n",
"0 8.26e-03 "
]
},
"execution_count": 29,
@ -991,7 +1001,8 @@
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>cell</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
@ -1002,23 +1013,24 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>(0.0e+00 - 6.2e-01)</td>\n",
" <td>10000</td>\n",
" <td>total</td>\n",
" <td>(nu-fission / absorption)</td>\n",
" <td>1.237053</td>\n",
" <td>0.011765</td>\n",
" <td> 0</td>\n",
" <td> 0.000001</td>\n",
" <td> 10000</td>\n",
" <td> total</td>\n",
" <td> (nu-fission / absorption)</td>\n",
" <td> 1.663616</td>\n",
" <td> 0.018624</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" energy [MeV] cell nuclide score mean \\\n",
"0 (0.0e+00 - 6.2e-01) 10000 total (nu-fission / absorption) 1.237053 \n",
" energy low [MeV] energy high [MeV] cell nuclide \\\n",
"0 0.00e+00 6.25e-07 10000 total \n",
"\n",
" std. dev. \n",
"0 0.011765 "
" score mean std. dev. \n",
"0 (nu-fission / absorption) 1.66e+00 1.86e-02 "
]
},
"execution_count": 30,
@ -1054,7 +1066,8 @@
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>cell</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
@ -1065,23 +1078,24 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>(0.0e+00 - 6.2e-01)</td>\n",
" <td>10000</td>\n",
" <td>total</td>\n",
" <td>(((absorption * nu-fission) * absorption) * (n...</td>\n",
" <td>1.040166</td>\n",
" <td>0.019018</td>\n",
" <td> 0</td>\n",
" <td> 0.000001</td>\n",
" <td> 10000</td>\n",
" <td> total</td>\n",
" <td> (((absorption * nu-fission) * absorption) * (n...</td>\n",
" <td> 1.040166</td>\n",
" <td> 0.021928</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" energy [MeV] cell nuclide \\\n",
"0 (0.0e+00 - 6.2e-01) 10000 total \n",
" energy low [MeV] energy high [MeV] cell nuclide \\\n",
"0 0.00e+00 6.25e-07 10000 total \n",
"\n",
" score mean std. dev. \n",
"0 (((absorption * nu-fission) * absorption) * (n... 1.040166 0.019018 "
" score mean std. dev. \n",
"0 (((absorption * nu-fission) * absorption) * (n... 1.04e+00 2.19e-02 "
]
},
"execution_count": 31,
@ -1135,7 +1149,8 @@
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
@ -1145,100 +1160,108 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>0.000001</td>\n",
" <td>7.377419e-09</td>\n",
" <td> 10000</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> (U-238 / total)</td>\n",
" <td> (nu-fission / flux)</td>\n",
" <td> 0.000001</td>\n",
" <td> 7.377419e-09</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>0.209989</td>\n",
" <td>2.303838e-03</td>\n",
" <td> 10000</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> (U-238 / total)</td>\n",
" <td> (scatter / flux)</td>\n",
" <td> 0.209989</td>\n",
" <td> 2.303838e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>0.356420</td>\n",
" <td>3.951669e-03</td>\n",
" <td> 10000</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> (U-235 / total)</td>\n",
" <td> (nu-fission / flux)</td>\n",
" <td> 0.356420</td>\n",
" <td> 3.951669e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>0.005555</td>\n",
" <td>6.101004e-05</td>\n",
" <td> 10000</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> (U-235 / total)</td>\n",
" <td> (scatter / flux)</td>\n",
" <td> 0.005555</td>\n",
" <td> 6.101004e-05</td>\n",
" </tr>\n",
" <tr>\n",
" <th>4</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>0.007155</td>\n",
" <td>8.053460e-05</td>\n",
" <td> 10000</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> (U-238 / total)</td>\n",
" <td> (nu-fission / flux)</td>\n",
" <td> 0.007155</td>\n",
" <td> 8.053460e-05</td>\n",
" </tr>\n",
" <tr>\n",
" <th>5</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>0.227770</td>\n",
" <td>1.079289e-03</td>\n",
" <td> 10000</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> (U-238 / total)</td>\n",
" <td> (scatter / flux)</td>\n",
" <td> 0.227770</td>\n",
" <td> 1.079289e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>6</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>0.008067</td>\n",
" <td>5.254797e-05</td>\n",
" <td> 10000</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> (U-235 / total)</td>\n",
" <td> (nu-fission / flux)</td>\n",
" <td> 0.008067</td>\n",
" <td> 5.254797e-05</td>\n",
" </tr>\n",
" <tr>\n",
" <th>7</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>0.003367</td>\n",
" <td>1.647058e-05</td>\n",
" <td> 10000</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> (U-235 / total)</td>\n",
" <td> (scatter / flux)</td>\n",
" <td> 0.003367</td>\n",
" <td> 1.647058e-05</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide score mean \\\n",
"0 10000 (0.0e+00 - 6.3e-07) (U-238 / total) (nu-fission / flux) 0.000001 \n",
"1 10000 (0.0e+00 - 6.3e-07) (U-238 / total) (scatter / flux) 0.209989 \n",
"2 10000 (0.0e+00 - 6.3e-07) (U-235 / total) (nu-fission / flux) 0.356420 \n",
"3 10000 (0.0e+00 - 6.3e-07) (U-235 / total) (scatter / flux) 0.005555 \n",
"4 10000 (6.3e-07 - 2.0e+01) (U-238 / total) (nu-fission / flux) 0.007155 \n",
"5 10000 (6.3e-07 - 2.0e+01) (U-238 / total) (scatter / flux) 0.227770 \n",
"6 10000 (6.3e-07 - 2.0e+01) (U-235 / total) (nu-fission / flux) 0.008067 \n",
"7 10000 (6.3e-07 - 2.0e+01) (U-235 / total) (scatter / flux) 0.003367 \n",
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
"0 10000 0.00e+00 6.25e-07 (U-238 / total) \n",
"1 10000 0.00e+00 6.25e-07 (U-238 / total) \n",
"2 10000 0.00e+00 6.25e-07 (U-235 / total) \n",
"3 10000 0.00e+00 6.25e-07 (U-235 / total) \n",
"4 10000 6.25e-07 2.00e+01 (U-238 / total) \n",
"5 10000 6.25e-07 2.00e+01 (U-238 / total) \n",
"6 10000 6.25e-07 2.00e+01 (U-235 / total) \n",
"7 10000 6.25e-07 2.00e+01 (U-235 / total) \n",
"\n",
" std. dev. \n",
"0 7.377419e-09 \n",
"1 2.303838e-03 \n",
"2 3.951669e-03 \n",
"3 6.101004e-05 \n",
"4 8.053460e-05 \n",
"5 1.079289e-03 \n",
"6 5.254797e-05 \n",
"7 1.647058e-05 "
" score mean std. dev. \n",
"0 (nu-fission / flux) 6.66e-07 7.38e-09 \n",
"1 (scatter / flux) 2.10e-01 2.30e-03 \n",
"2 (nu-fission / flux) 3.56e-01 3.95e-03 \n",
"3 (scatter / flux) 5.56e-03 6.10e-05 \n",
"4 (nu-fission / flux) 7.15e-03 8.05e-05 \n",
"5 (scatter / flux) 2.28e-01 1.08e-03 \n",
"6 (nu-fission / flux) 8.07e-03 5.25e-05 \n",
"7 (scatter / flux) 3.37e-03 1.65e-05 "
]
},
"execution_count": 33,
@ -1361,7 +1384,8 @@
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
@ -1371,50 +1395,60 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>U-238</td>\n",
" <td>nu-fission</td>\n",
" <td>0.000002</td>\n",
" <td>1.283958e-08</td>\n",
" <td> 10000</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> U-238</td>\n",
" <td> nu-fission</td>\n",
" <td> 0.000002</td>\n",
" <td> 1.283958e-08</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>U-235</td>\n",
" <td>nu-fission</td>\n",
" <td>0.868553</td>\n",
" <td>6.880390e-03</td>\n",
" <td> 10000</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
" <td> U-235</td>\n",
" <td> nu-fission</td>\n",
" <td> 0.868553</td>\n",
" <td> 6.880390e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>U-238</td>\n",
" <td>nu-fission</td>\n",
" <td>0.082149</td>\n",
" <td>8.837250e-04</td>\n",
" <td> 10000</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> U-238</td>\n",
" <td> nu-fission</td>\n",
" <td> 0.082149</td>\n",
" <td> 8.837250e-04</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>U-235</td>\n",
" <td>nu-fission</td>\n",
" <td>0.092618</td>\n",
" <td>5.195308e-04</td>\n",
" <td> 10000</td>\n",
" <td> 0.000001</td>\n",
" <td> 20.000000</td>\n",
" <td> U-235</td>\n",
" <td> nu-fission</td>\n",
" <td> 0.092618</td>\n",
" <td> 5.195308e-04</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide score mean std. dev.\n",
"0 10000 (0.0e+00 - 6.3e-07) U-238 nu-fission 0.000002 1.283958e-08\n",
"1 10000 (0.0e+00 - 6.3e-07) U-235 nu-fission 0.868553 6.880390e-03\n",
"2 10000 (6.3e-07 - 2.0e+01) U-238 nu-fission 0.082149 8.837250e-04\n",
"3 10000 (6.3e-07 - 2.0e+01) U-235 nu-fission 0.092618 5.195308e-04"
" cell energy low [MeV] energy high [MeV] nuclide score mean \\\n",
"0 10000 0.00e+00 6.25e-07 U-238 nu-fission 1.62e-06 \n",
"1 10000 0.00e+00 6.25e-07 U-235 nu-fission 8.69e-01 \n",
"2 10000 6.25e-07 2.00e+01 U-238 nu-fission 8.21e-02 \n",
"3 10000 6.25e-07 2.00e+01 U-235 nu-fission 9.26e-02 \n",
"\n",
" std. dev. \n",
"0 1.28e-08 \n",
"1 6.88e-03 \n",
"2 8.84e-04 \n",
"3 5.20e-04 "
]
},
"execution_count": 37,
@ -1444,7 +1478,8 @@
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>energy low [MeV]</th>\n",
" <th>energy high [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
@ -1454,100 +1489,120 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>10002</td>\n",
" <td>(1.0e-08 - 1.1e-07)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>4.619398</td>\n",
" <td>0.040124</td>\n",
" <td> 10002</td>\n",
" <td> 1.000000e-08</td>\n",
" <td> 0.000000</td>\n",
" <td> H-1</td>\n",
" <td> scatter</td>\n",
" <td> 4.619398</td>\n",
" <td> 0.040124</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>10002</td>\n",
" <td>(1.1e-07 - 1.2e-06)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.030757</td>\n",
" <td>0.011239</td>\n",
" <td> 10002</td>\n",
" <td> 1.080060e-07</td>\n",
" <td> 0.000001</td>\n",
" <td> H-1</td>\n",
" <td> scatter</td>\n",
" <td> 2.030757</td>\n",
" <td> 0.011239</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
" <td>10002</td>\n",
" <td>(1.2e-06 - 1.3e-05)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>1.658488</td>\n",
" <td>0.009777</td>\n",
" <td> 10002</td>\n",
" <td> 1.166529e-06</td>\n",
" <td> 0.000013</td>\n",
" <td> H-1</td>\n",
" <td> scatter</td>\n",
" <td> 1.658488</td>\n",
" <td> 0.009777</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
" <td>10002</td>\n",
" <td>(1.3e-05 - 1.4e-04)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>1.853002</td>\n",
" <td>0.007378</td>\n",
" <td> 10002</td>\n",
" <td> 1.259921e-05</td>\n",
" <td> 0.000136</td>\n",
" <td> H-1</td>\n",
" <td> scatter</td>\n",
" <td> 1.853002</td>\n",
" <td> 0.007378</td>\n",
" </tr>\n",
" <tr>\n",
" <th>4</th>\n",
" <td>10002</td>\n",
" <td>(1.4e-04 - 1.5e-03)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.050773</td>\n",
" <td>0.012484</td>\n",
" <td> 10002</td>\n",
" <td> 1.360790e-04</td>\n",
" <td> 0.001470</td>\n",
" <td> H-1</td>\n",
" <td> scatter</td>\n",
" <td> 2.050773</td>\n",
" <td> 0.012484</td>\n",
" </tr>\n",
" <tr>\n",
" <th>5</th>\n",
" <td>10002</td>\n",
" <td>(1.5e-03 - 1.6e-02)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.131759</td>\n",
" <td>0.007821</td>\n",
" <td> 10002</td>\n",
" <td> 1.469734e-03</td>\n",
" <td> 0.015874</td>\n",
" <td> H-1</td>\n",
" <td> scatter</td>\n",
" <td> 2.131759</td>\n",
" <td> 0.007821</td>\n",
" </tr>\n",
" <tr>\n",
" <th>6</th>\n",
" <td>10002</td>\n",
" <td>(1.6e-02 - 1.7e-01)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.213710</td>\n",
" <td>0.015159</td>\n",
" <td> 10002</td>\n",
" <td> 1.587401e-02</td>\n",
" <td> 0.171449</td>\n",
" <td> H-1</td>\n",
" <td> scatter</td>\n",
" <td> 2.213710</td>\n",
" <td> 0.015159</td>\n",
" </tr>\n",
" <tr>\n",
" <th>7</th>\n",
" <td>10002</td>\n",
" <td>(1.7e-01 - 1.9e+00)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.011925</td>\n",
" <td>0.009406</td>\n",
" <td> 10002</td>\n",
" <td> 1.714488e-01</td>\n",
" <td> 1.851749</td>\n",
" <td> H-1</td>\n",
" <td> scatter</td>\n",
" <td> 2.011925</td>\n",
" <td> 0.009406</td>\n",
" </tr>\n",
" <tr>\n",
" <th>8</th>\n",
" <td>10002</td>\n",
" <td>(1.9e+00 - 2.0e+01)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>0.371280</td>\n",
" <td>0.003949</td>\n",
" <td> 10002</td>\n",
" <td> 1.851749e+00</td>\n",
" <td> 20.000000</td>\n",
" <td> H-1</td>\n",
" <td> scatter</td>\n",
" <td> 0.371280</td>\n",
" <td> 0.003949</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide score mean std. dev.\n",
"0 10002 (1.0e-08 - 1.1e-07) H-1 scatter 4.619398 0.040124\n",
"1 10002 (1.1e-07 - 1.2e-06) H-1 scatter 2.030757 0.011239\n",
"2 10002 (1.2e-06 - 1.3e-05) H-1 scatter 1.658488 0.009777\n",
"3 10002 (1.3e-05 - 1.4e-04) H-1 scatter 1.853002 0.007378\n",
"4 10002 (1.4e-04 - 1.5e-03) H-1 scatter 2.050773 0.012484\n",
"5 10002 (1.5e-03 - 1.6e-02) H-1 scatter 2.131759 0.007821\n",
"6 10002 (1.6e-02 - 1.7e-01) H-1 scatter 2.213710 0.015159\n",
"7 10002 (1.7e-01 - 1.9e+00) H-1 scatter 2.011925 0.009406\n",
"8 10002 (1.9e+00 - 2.0e+01) H-1 scatter 0.371280 0.003949"
" cell energy low [MeV] energy high [MeV] nuclide score mean \\\n",
"0 10002 1.00e-08 1.08e-07 H-1 scatter 4.62e+00 \n",
"1 10002 1.08e-07 1.17e-06 H-1 scatter 2.03e+00 \n",
"2 10002 1.17e-06 1.26e-05 H-1 scatter 1.66e+00 \n",
"3 10002 1.26e-05 1.36e-04 H-1 scatter 1.85e+00 \n",
"4 10002 1.36e-04 1.47e-03 H-1 scatter 2.05e+00 \n",
"5 10002 1.47e-03 1.59e-02 H-1 scatter 2.13e+00 \n",
"6 10002 1.59e-02 1.71e-01 H-1 scatter 2.21e+00 \n",
"7 10002 1.71e-01 1.85e+00 H-1 scatter 2.01e+00 \n",
"8 10002 1.85e+00 2.00e+01 H-1 scatter 3.71e-01 \n",
"\n",
" std. dev. \n",
"0 4.01e-02 \n",
"1 1.12e-02 \n",
"2 9.78e-03 \n",
"3 7.38e-03 \n",
"4 1.25e-02 \n",
"5 7.82e-03 \n",
"6 1.52e-02 \n",
"7 9.41e-03 \n",
"8 3.95e-03 "
]
},
"execution_count": 38,

View file

@ -502,9 +502,9 @@ class Filter(object):
2. separate columns for the cell IDs, universe IDs, and lattice IDs
and x,y,z cell indices corresponding to each (with summary info).
For 'energy' and 'energyout' filters, the DataFrame include a single
column with each element comprising a string with the lower, upper
energy bounds for each filter bin.
For 'energy' and 'energyout' filters, the DataFrame includes one
column for the lower energy bound and one column for the upper
energy bound for each filter bin.
For 'mesh' filters, the DataFrame includes three columns for the
x,y,z mesh cell indices corresponding to each filter bin.
@ -673,9 +673,11 @@ class Filter(object):
# Assign entry to Lattice Multi-index column
else:
# Reverse y index per lattice ordering in OpenCG
level_dict[lat_id_key][offset] = coords._lattice._id
level_dict[lat_x_key][offset] = coords._lat_x
level_dict[lat_y_key][offset] = coords._lat_y
level_dict[lat_y_key][offset] = \
coords._lattice.dimension[1] - coords._lat_y - 1
level_dict[lat_z_key][offset] = coords._lat_z
# Move to next node in LocalCoords linked list
@ -717,21 +719,30 @@ class Filter(object):
# energy, energyout filters
elif 'energy' in self.type:
bins = self.bins
num_bins = self.num_bins
# Extract the lower and upper energy bounds, then repeat and tile
# them as necessary to account for other filters.
lo_bins = np.repeat(self.bins[:-1], self.stride)
hi_bins = np.repeat(self.bins[1:], self.stride)
tile_factor = data_size / len(lo_bins)
lo_bins = np.tile(lo_bins, tile_factor)
hi_bins = np.tile(hi_bins, tile_factor)
# Create strings for
template = '({0:.1e} - {1:.1e})'
filter_bins = []
for i in range(num_bins):
filter_bins.append(template.format(bins[i], bins[i+1]))
# Add the new energy columns to the DataFrame.
df.loc[:, self.type + ' low [MeV]'] = lo_bins
df.loc[:, self.type + ' high [MeV]'] = hi_bins
# Tile the energy bins into a DataFrame column
filter_bins = np.repeat(filter_bins, self.stride)
tile_factor = data_size / len(filter_bins)
filter_bins = np.tile(filter_bins, tile_factor)
filter_bins = filter_bins
df = pd.concat([df, pd.DataFrame({self.type + ' [MeV]' : filter_bins})])
elif self.type in ('azimuthal', 'polar'):
# Extract the lower and upper angle bounds, then repeat and tile
# them as necessary to account for other filters.
lo_bins = np.repeat(self.bins[:-1], self.stride)
hi_bins = np.repeat(self.bins[1:], self.stride)
tile_factor = data_size / len(lo_bins)
lo_bins = np.tile(lo_bins, tile_factor)
hi_bins = np.tile(hi_bins, tile_factor)
# Add the new angle columns to the DataFrame.
df.loc[:, self.type + ' low'] = lo_bins
df.loc[:, self.type + ' high'] = hi_bins
# universe, material, surface, cell, and cellborn filters
else:

View file

@ -1232,28 +1232,35 @@ class MGXS(object):
# Override energy groups bounds with indices
all_groups = np.arange(self.num_groups, 0, -1, dtype=np.int)
all_groups = np.repeat(all_groups, self.num_nuclides)
if 'energy [MeV]' in df and 'energyout [MeV]' in df:
df.rename(columns={'energy [MeV]': 'group in'}, inplace=True)
if 'energy low [MeV]' in df and 'energyout low [MeV]' in df:
df.rename(columns={'energy low [MeV]': 'group in'},
inplace=True)
in_groups = np.tile(all_groups, self.num_subdomains)
in_groups = np.repeat(in_groups, self.num_groups)
df['group in'] = in_groups
del df['energy high [MeV]']
df.rename(columns={'energyout [MeV]': 'group out'}, inplace=True)
df.rename(columns={'energyout low [MeV]': 'group out'},
inplace=True)
out_groups = \
np.tile(all_groups, self.num_subdomains * self.num_groups)
df['group out'] = out_groups
del df['energyout high [MeV]']
columns = ['group in', 'group out']
elif 'energyout [MeV]' in df:
df.rename(columns={'energyout [MeV]': 'group out'}, inplace=True)
elif 'energyout low [MeV]' in df:
df.rename(columns={'energyout low [MeV]': 'group out'},
inplace=True)
in_groups = np.tile(all_groups, self.num_subdomains)
df['group out'] = in_groups
del df['energyout high [MeV]']
columns = ['group out']
elif 'energy [MeV]' in df:
df.rename(columns={'energy [MeV]': 'group in'}, inplace=True)
elif 'energy low [MeV]' in df:
df.rename(columns={'energy low [MeV]': 'group in'}, inplace=True)
in_groups = np.tile(all_groups, self.num_subdomains)
df['group in'] = in_groups
del df['energy high [MeV]']
columns = ['group in']
# Select out those groups the user requested

View file

@ -372,7 +372,7 @@ class Summary(object):
# Set the distribcell offsets for the lattice
if offsets is not None:
lattice.offsets = offsets
lattice.offsets = offsets[:, ::-1, :]
# Add the Lattice to the global dictionary of all Lattices
self.lattices[index] = lattice

View file

@ -2,6 +2,7 @@ from __future__ import division
from collections import Iterable, defaultdict
import copy
from functools import partial
import os
import pickle
import itertools
@ -1244,7 +1245,7 @@ class Tally(object):
return data
def get_pandas_dataframe(self, filters=True, nuclides=True,
scores=True, summary=None):
scores=True, summary=None, float_format='{:.2e}'):
"""Build a Pandas DataFrame for the Tally data.
This method constructs a Pandas DataFrame object for the Tally data
@ -1268,6 +1269,9 @@ class Tally(object):
information in the Summary object is embedded into a Multi-index
column with a geometric "path" to each distribcell intance.
NOTE: This option requires the OpenCG Python package.
float_format : string
All floats in the DataFrame will be formatted using the given
format string before printing.
Returns
-------
@ -1367,6 +1371,10 @@ class Tally(object):
# Create and set a MultiIndex for the DataFrame's columns
df.columns = pd.MultiIndex.from_tuples(columns)
# Modify the df.to_string method so that it prints formatted strings.
# Credit to http://stackoverflow.com/users/3657742/chrisb for this trick
df.to_string = partial(df.to_string, float_format=float_format.format)
return df
def get_reshaped_data(self, value='mean'):
@ -2748,7 +2756,7 @@ class Tally(object):
bin_indices.append(bin_index)
num_bins += 1
find_filter.bins = set(find_filter.bins[bin_indices])
find_filter.bins = np.unique(find_filter.bins[bin_indices])
find_filter.num_bins = num_bins
# Update the new tally's filter strides

View file

@ -32,7 +32,7 @@ kwargs = {'name': 'openmc',
if have_setuptools:
kwargs.update({
# Required dependencies
'install_requires': ['numpy', 'h5py', 'matplotlib'],
'install_requires': ['numpy>=1.9', 'h5py', 'matplotlib'],
# Optional dependencies
'extras_require': {

View file

@ -0,0 +1 @@
b9b4222c4beea80fe6083590f6b785303d174972d80671fb661bac8e030db6f4a61648240cfad6162799361fc0e08a23c61d31aff844d978528d6dad5b5fbc63

View file

@ -0,0 +1 @@
b5f96919ca474cd1c9c9d0acde3b8aac4a1cf636443c72a38b6c5a4221a8ce3e90182aaef2f664e44b9175ca257a89db2328b63e19388ee0e5006de4b3d92ce6

View file

@ -0,0 +1,129 @@
#!/usr/bin/env python
import os
import sys
import glob
import hashlib
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
import openmc
from openmc.source import Source
from openmc.stats import Box
class AsymmetricLatticeTestHarness(PyAPITestHarness):
def _build_inputs(self):
"""Build an axis-asymmetric lattice of fuel assemblies"""
# Build full core geometry from underlying input set
self._input_set.build_default_materials_and_geometry()
# Extract all universes from the full core geometry
geometry = self._input_set.geometry.geometry
all_univs = geometry.get_all_universes()
# Extract universes encapsulating fuel and water assemblies
water = all_univs[7]
fuel = all_univs[8]
# Construct a 3x3 lattice of fuel assemblies
core_lat = openmc.RectLattice(name='3x3 Core Lattice', lattice_id=202)
core_lat.dimension = (3, 3)
core_lat.lower_left = (-32.13, -32.13)
core_lat.pitch = (21.42, 21.42)
core_lat.universes = [[fuel, water, water],
[fuel, fuel, fuel],
[water, water, water]]
# Create bounding surfaces
min_x = openmc.XPlane(x0=-32.13, boundary_type='reflective')
max_x = openmc.XPlane(x0=+32.13, boundary_type='reflective')
min_y = openmc.YPlane(y0=-32.13, boundary_type='reflective')
max_y = openmc.YPlane(y0=+32.13, boundary_type='reflective')
min_z = openmc.ZPlane(z0=0, boundary_type='reflective')
max_z = openmc.ZPlane(z0=+32.13, boundary_type='reflective')
# Define root universe
root_univ = openmc.Universe(universe_id=0, name='root universe')
root_cell = openmc.Cell(cell_id=1)
root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z
root_cell.fill = core_lat
root_univ.add_cell(root_cell)
# Over-ride geometry in the input set with this 3x3 lattice
self._input_set.geometry.geometry.root_universe = root_univ
# Initialize a "distribcell" filter for the fuel pin cell
distrib_filter = openmc.Filter(type='distribcell', bins=[27])
# Initialize the tallies
tally = openmc.Tally(name='distribcell tally', tally_id=27)
tally.add_filter(distrib_filter)
tally.add_score('nu-fission')
# Initialize the tallies file
tallies_file = openmc.TalliesFile()
tallies_file.add_tally(tally)
# Assign the tallies file to the input set
self._input_set.tallies = tallies_file
# Build default settings
self._input_set.build_default_settings()
# Specify summary output and correct source sampling box
source = Source(space=Box([-32, -32, 0], [32, 32, 32]))
source.space.only_fissionable = True
self._input_set.settings.source = source
self._input_set.settings.output = {'summary': True}
# Write input XML files
self._input_set.export()
def _get_results(self, hash_output=True):
"""Digest info in statepoint and summary and return as a string."""
# Read the statepoint file
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
sp = openmc.StatePoint(statepoint)
# Read the summary file
summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0]
su = openmc.Summary(summary)
sp.link_with_summary(su)
# Extract the tally of interest
tally = sp.get_tally(name='distribcell tally')
# Create a string of all mean, std. dev. values for both tallies
outstr = ''
outstr += ', '.join(map(str, tally.mean.flatten())) + '\n'
outstr += ', '.join(map(str, tally.std_dev.flatten())) + '\n'
# Extract fuel assembly lattices from the summary
all_cells = su.openmc_geometry.get_all_cells()
fuel = all_cells[80].fill
core = all_cells[1].fill
# Append a string of lattice distribcell offsets to the string
outstr += ', '.join(map(str, fuel.offsets.flatten())) + '\n'
outstr += ', '.join(map(str, core.offsets.flatten())) + '\n'
# Hash the results if necessary
if hash_output:
sha512 = hashlib.sha512()
sha512.update(outstr.encode('utf-8'))
outstr = sha512.hexdigest()
return outstr
def _cleanup(self):
super(AsymmetricLatticeTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = AsymmetricLatticeTestHarness('statepoint.10.h5', True)
harness.main()