Merge branch 'develop' into volume

This commit is contained in:
Paul Romano 2017-02-27 07:26:25 -06:00
commit a4dbcca90d
15 changed files with 594 additions and 1507 deletions

File diff suppressed because one or more lines are too long

View file

@ -369,21 +369,21 @@
"\n",
"* `TotalXS`\n",
"* `TransportXS`\n",
"* `NuTransportXS`\n",
"* `AbsorptionXS`\n",
"* `CaptureXS`\n",
"* `FissionXS`\n",
"* `NuFissionXS`\n",
"* `KappaFissionXS`\n",
"* `ScatterXS`\n",
"* `NuScatterXS`\n",
"* `ScatterMatrixXS`\n",
"* `NuScatterMatrixXS`\n",
"* `Chi`\n",
"* `ChiPrompt`\n",
"* `InverseVelocity`\n",
"* `PromptNuFissionXS`\n",
"\n",
"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",
"\n",
"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",
"\n",
"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."
]
},
@ -398,7 +398,11 @@
"# Instantiate a few different sections\n",
"total = mgxs.TotalXS(domain=cell, groups=groups)\n",
"absorption = mgxs.AbsorptionXS(domain=cell, groups=groups)\n",
"scattering = mgxs.ScatterXS(domain=cell, groups=groups)"
"scattering = mgxs.ScatterXS(domain=cell, groups=groups)\n",
"\n",
"# Note that if we wanted to incorporate neutron multiplication in the\n",
"# scattering cross section we would write the previous line as:\n",
"# scattering = mgxs.ScatterXS(domain=cell, groups=groups, nu=True)"
]
},
{
@ -520,8 +524,8 @@
" 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 | 54b65c8bda6af5788bd762b8cf9855d1a8008238\n",
" Date/Time | 2017-02-12 13:36:24\n",
" Git SHA1 | 60a1f157dae88b62e1865a5fe3efd7ef0773a068\n",
" Date/Time | 2017-02-25 14:26:54\n",
" OpenMP Threads | 8\n",
"\n",
" ===========================================================================\n",
@ -592,7 +596,7 @@
" 42/1 1.13779 1.16177 +/- 0.00531\n",
" 43/1 1.15066 1.16143 +/- 0.00516\n",
" 44/1 1.12174 1.16026 +/- 0.00514\n",
" 45/1 1.17479 1.16068 +/- 0.00501\n",
" 45/1 1.17478 1.16068 +/- 0.00501\n",
" 46/1 1.14146 1.16014 +/- 0.00489\n",
" 47/1 1.20464 1.16135 +/- 0.00491\n",
" 48/1 1.15119 1.16108 +/- 0.00479\n",
@ -607,20 +611,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 4.1327E-01 seconds\n",
" Reading cross sections = 3.2638E-01 seconds\n",
" Total time in simulation = 2.2324E+00 seconds\n",
" Time in transport only = 2.1226E+00 seconds\n",
" Time in inactive batches = 3.0650E-01 seconds\n",
" Time in active batches = 1.9259E+00 seconds\n",
" Time synchronizing fission bank = 2.7640E-03 seconds\n",
" Sampling source sites = 2.0198E-03 seconds\n",
" SEND/RECV source sites = 7.0929E-04 seconds\n",
" Time accumulating tallies = 4.5355E-05 seconds\n",
" Total time for finalization = 4.1885E-04 seconds\n",
" Total time elapsed = 2.6534E+00 seconds\n",
" Calculation Rate (inactive) = 81567.1 neutrons/second\n",
" Calculation Rate (active) = 51923.2 neutrons/second\n",
" Total time for initialization = 3.5070E-01 seconds\n",
" Reading cross sections = 2.4151E-01 seconds\n",
" Total time in simulation = 2.3276E+00 seconds\n",
" Time in transport only = 2.2350E+00 seconds\n",
" Time in inactive batches = 2.5677E-01 seconds\n",
" Time in active batches = 2.0708E+00 seconds\n",
" Time synchronizing fission bank = 2.7683E-03 seconds\n",
" Sampling source sites = 2.0233E-03 seconds\n",
" SEND/RECV source sites = 7.1007E-04 seconds\n",
" Time accumulating tallies = 5.0753E-05 seconds\n",
" Total time for finalization = 3.8695E-04 seconds\n",
" Total time elapsed = 2.6857E+00 seconds\n",
" Calculation Rate (inactive) = 97364.6 neutrons/second\n",
" Calculation Rate (active) = 48290.8 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
@ -901,7 +905,7 @@
" <td>6.250000e-01</td>\n",
" <td>total</td>\n",
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td>-2.664535e-15</td>\n",
" <td>-5.551115e-15</td>\n",
" <td>0.011292</td>\n",
" </tr>\n",
" <tr>\n",
@ -911,7 +915,7 @@
" <td>2.000000e+07</td>\n",
" <td>total</td>\n",
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td>-3.330669e-16</td>\n",
" <td>-1.110223e-16</td>\n",
" <td>0.002570</td>\n",
" </tr>\n",
" </tbody>\n",
@ -924,8 +928,8 @@
"1 1 6.25e-01 2.00e+07 total \n",
"\n",
" score mean std. dev. \n",
"0 (((total / flux) - (absorption / flux)) - (sca... -2.66e-15 1.13e-02 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... -3.33e-16 2.57e-03 "
"0 (((total / flux) - (absorption / flux)) - (sca... -5.55e-15 1.13e-02 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... -1.11e-16 2.57e-03 "
]
},
"execution_count": 22,

File diff suppressed because one or more lines are too long

File diff suppressed because one or more lines are too long

File diff suppressed because one or more lines are too long