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Workingto integrate consistent scattering matrices with consolidation made by @nelsonag
This commit is contained in:
Will Boyd
commit
0495ff7eab
71 changed files with 3445 additions and 5009 deletions
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@ -369,21 +369,21 @@
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"\n",
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"* `TotalXS`\n",
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"* `TransportXS`\n",
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"* `NuTransportXS`\n",
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"* `AbsorptionXS`\n",
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"* `CaptureXS`\n",
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"* `FissionXS`\n",
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"* `NuFissionXS`\n",
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"* `KappaFissionXS`\n",
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"* `ScatterXS`\n",
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"* `NuScatterXS`\n",
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"* `ScatterMatrixXS`\n",
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"* `NuScatterMatrixXS`\n",
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"* `Chi`\n",
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"* `ChiPrompt`\n",
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"* `InverseVelocity`\n",
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"* `PromptNuFissionXS`\n",
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"\n",
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"Of course, we are aware that the fission cross section (`FissionXS`) can sometimes be paired with the fission neutron multiplication to become $\\nu\\sigma_f$. This can be accomodated in to the `FissionXS` class by setting the `nu` parameter to `True` as shown below.\n",
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"\n",
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"Additionally, scattering reactions (like (n,2n)) can also be defined to take in to account the neutron multiplication to become $\\nu\\sigma_s$. This can be accomodated in the the transport (`TransportXS`), scattering (`ScatterXS`), and scattering-matrix (`ScatterMatrixXS`) cross sections types by setting the `nu` parameter to `True` as shown below.\n",
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"\n",
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"These classes provide us with an interface to generate the tally inputs as well as perform post-processing of OpenMC's tally data to compute the respective multi-group cross sections. In this case, let's create the multi-group total, absorption and scattering cross sections with our 2-group structure."
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]
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},
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@ -398,7 +398,11 @@
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"# Instantiate a few different sections\n",
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"total = mgxs.TotalXS(domain=cell, groups=groups)\n",
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"absorption = mgxs.AbsorptionXS(domain=cell, groups=groups)\n",
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"scattering = mgxs.ScatterXS(domain=cell, groups=groups)"
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"scattering = mgxs.ScatterXS(domain=cell, groups=groups)\n",
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"\n",
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"# Note that if we wanted to incorporate neutron multiplication in the\n",
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"# scattering cross section we would write the previous line as:\n",
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"# scattering = mgxs.ScatterXS(domain=cell, groups=groups, nu=True)"
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]
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},
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{
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@ -520,8 +524,8 @@
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" Copyright | 2011-2017 Massachusetts Institute of Technology\n",
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" License | http://openmc.readthedocs.io/en/latest/license.html\n",
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" Version | 0.8.0\n",
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" Git SHA1 | 54b65c8bda6af5788bd762b8cf9855d1a8008238\n",
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" Date/Time | 2017-02-12 13:36:24\n",
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" Git SHA1 | 60a1f157dae88b62e1865a5fe3efd7ef0773a068\n",
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" Date/Time | 2017-02-25 14:26:54\n",
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" OpenMP Threads | 8\n",
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"\n",
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" ===========================================================================\n",
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@ -592,7 +596,7 @@
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" 42/1 1.13779 1.16177 +/- 0.00531\n",
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" 43/1 1.15066 1.16143 +/- 0.00516\n",
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" 44/1 1.12174 1.16026 +/- 0.00514\n",
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" 45/1 1.17479 1.16068 +/- 0.00501\n",
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" 45/1 1.17478 1.16068 +/- 0.00501\n",
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" 46/1 1.14146 1.16014 +/- 0.00489\n",
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" 47/1 1.20464 1.16135 +/- 0.00491\n",
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" 48/1 1.15119 1.16108 +/- 0.00479\n",
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@ -607,20 +611,20 @@
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"\n",
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" =======================> TIMING STATISTICS <=======================\n",
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"\n",
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" Total time for initialization = 4.1327E-01 seconds\n",
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" Reading cross sections = 3.2638E-01 seconds\n",
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" Total time in simulation = 2.2324E+00 seconds\n",
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" Time in transport only = 2.1226E+00 seconds\n",
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" Time in inactive batches = 3.0650E-01 seconds\n",
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" Time in active batches = 1.9259E+00 seconds\n",
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" Time synchronizing fission bank = 2.7640E-03 seconds\n",
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" Sampling source sites = 2.0198E-03 seconds\n",
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" SEND/RECV source sites = 7.0929E-04 seconds\n",
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" Time accumulating tallies = 4.5355E-05 seconds\n",
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" Total time for finalization = 4.1885E-04 seconds\n",
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" Total time elapsed = 2.6534E+00 seconds\n",
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" Calculation Rate (inactive) = 81567.1 neutrons/second\n",
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" Calculation Rate (active) = 51923.2 neutrons/second\n",
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" Total time for initialization = 3.5070E-01 seconds\n",
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" Reading cross sections = 2.4151E-01 seconds\n",
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" Total time in simulation = 2.3276E+00 seconds\n",
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" Time in transport only = 2.2350E+00 seconds\n",
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" Time in inactive batches = 2.5677E-01 seconds\n",
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" Time in active batches = 2.0708E+00 seconds\n",
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" Time synchronizing fission bank = 2.7683E-03 seconds\n",
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" Sampling source sites = 2.0233E-03 seconds\n",
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" SEND/RECV source sites = 7.1007E-04 seconds\n",
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" Time accumulating tallies = 5.0753E-05 seconds\n",
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" Total time for finalization = 3.8695E-04 seconds\n",
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" Total time elapsed = 2.6857E+00 seconds\n",
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" Calculation Rate (inactive) = 97364.6 neutrons/second\n",
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" Calculation Rate (active) = 48290.8 neutrons/second\n",
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"\n",
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" ============================> RESULTS <============================\n",
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"\n",
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@ -901,7 +905,7 @@
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" <td>6.250000e-01</td>\n",
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" <td>total</td>\n",
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" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
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" <td>-2.664535e-15</td>\n",
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" <td>-5.551115e-15</td>\n",
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" <td>0.011292</td>\n",
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" </tr>\n",
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" <tr>\n",
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@ -911,7 +915,7 @@
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" <td>2.000000e+07</td>\n",
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" <td>total</td>\n",
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" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
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" <td>-3.330669e-16</td>\n",
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" <td>-1.110223e-16</td>\n",
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" <td>0.002570</td>\n",
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" </tr>\n",
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" </tbody>\n",
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@ -924,8 +928,8 @@
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"1 1 6.25e-01 2.00e+07 total \n",
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"\n",
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" score mean std. dev. \n",
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"0 (((total / flux) - (absorption / flux)) - (sca... -2.66e-15 1.13e-02 \n",
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"1 (((total / flux) - (absorption / flux)) - (sca... -3.33e-16 2.57e-03 "
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"0 (((total / flux) - (absorption / flux)) - (sca... -5.55e-15 1.13e-02 \n",
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"1 (((total / flux) - (absorption / flux)) - (sca... -1.11e-16 2.57e-03 "
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]
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},
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"execution_count": 22,
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