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

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Sterling Harper 2016-04-11 17:31:17 -04:00
commit 435b9015b1
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2
.travis.yml
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@ -27,7 +27,7 @@ before_install:
- conda config --set always_yes yes --set changeps1 no
- conda update -q conda
- conda info -a
- conda create -q -n test-environment python=$TRAVIS_PYTHON_VERSION numpy scipy h5py pandas
- conda create -q -n test-environment python=$TRAVIS_PYTHON_VERSION numpy scipy h5py=2.5 pandas
- source activate test-environment
# Install GCC, MPICH, HDF5, PHDF5

8
docs/source/pythonapi/energy_groups.rst
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@ -1,8 +0,0 @@
.. _pythonapi_energy_groups:
=============
Energy Groups
=============
.. automodule:: openmc.mgxs.groups
:members:

307
docs/source/pythonapi/examples/mgxs-part-i.ipynb
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@ -518,9 +518,10 @@
" 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: 34381b40a9445a727e360873aaa6ef892af1cb6a\n",
" Date/Time: 2016-02-07 15:58:16\n",
" Git SHA1: 5f252e2df51930b9175fd41bafa8db01f3eaeb92\n",
" Date/Time: 2016-03-23 14:42:51\n",
" MPI Processes: 1\n",
" OpenMP Threads: 16\n",
"\n",
" ===========================================================================\n",
" ========================> INITIALIZATION <=========================\n",
@ -546,56 +547,56 @@
"\n",
" Bat./Gen. k Average k \n",
" ========= ======== ==================== \n",
" 1/1 1.19804 \n",
" 2/1 1.12945 \n",
" 3/1 1.15573 \n",
" 4/1 1.13929 \n",
" 5/1 1.16300 \n",
" 6/1 1.22117 \n",
" 7/1 1.19012 \n",
" 8/1 1.11299 \n",
" 9/1 1.16066 \n",
" 10/1 1.12566 \n",
" 11/1 1.20854 \n",
" 12/1 1.14691 1.17773 +/- 0.03082\n",
" 13/1 1.17204 1.17583 +/- 0.01789\n",
" 14/1 1.14148 1.16724 +/- 0.01529\n",
" 15/1 1.17272 1.16834 +/- 0.01189\n",
" 16/1 1.18575 1.17124 +/- 0.01014\n",
" 17/1 1.20498 1.17606 +/- 0.00983\n",
" 18/1 1.14754 1.17249 +/- 0.00923\n",
" 19/1 1.18141 1.17348 +/- 0.00820\n",
" 20/1 1.15074 1.17121 +/- 0.00768\n",
" 21/1 1.15914 1.17011 +/- 0.00703\n",
" 22/1 1.14586 1.16809 +/- 0.00673\n",
" 23/1 1.18999 1.16978 +/- 0.00642\n",
" 24/1 1.15101 1.16844 +/- 0.00609\n",
" 25/1 1.13791 1.16640 +/- 0.00602\n",
" 26/1 1.19791 1.16837 +/- 0.00597\n",
" 27/1 1.19818 1.17012 +/- 0.00587\n",
" 28/1 1.14160 1.16854 +/- 0.00576\n",
" 29/1 1.11487 1.16571 +/- 0.00614\n",
" 30/1 1.17538 1.16620 +/- 0.00584\n",
" 31/1 1.20210 1.16791 +/- 0.00581\n",
" 32/1 1.20078 1.16940 +/- 0.00574\n",
" 33/1 1.14624 1.16839 +/- 0.00558\n",
" 34/1 1.14618 1.16747 +/- 0.00542\n",
" 35/1 1.16866 1.16752 +/- 0.00520\n",
" 36/1 1.18565 1.16821 +/- 0.00504\n",
" 37/1 1.16824 1.16821 +/- 0.00485\n",
" 38/1 1.18299 1.16874 +/- 0.00471\n",
" 39/1 1.21418 1.17031 +/- 0.00480\n",
" 40/1 1.11167 1.16835 +/- 0.00504\n",
" 41/1 1.11545 1.16665 +/- 0.00516\n",
" 42/1 1.11114 1.16491 +/- 0.00529\n",
" 43/1 1.14227 1.16423 +/- 0.00517\n",
" 44/1 1.14104 1.16355 +/- 0.00506\n",
" 45/1 1.16756 1.16366 +/- 0.00492\n",
" 46/1 1.13065 1.16274 +/- 0.00487\n",
" 47/1 1.11251 1.16139 +/- 0.00492\n",
" 48/1 1.14731 1.16101 +/- 0.00481\n",
" 49/1 1.16691 1.16117 +/- 0.00469\n",
" 50/1 1.19679 1.16206 +/- 0.00465\n",
" 1/1 1.11184 \n",
" 2/1 1.15820 \n",
" 3/1 1.18468 \n",
" 4/1 1.17492 \n",
" 5/1 1.19645 \n",
" 6/1 1.18436 \n",
" 7/1 1.14070 \n",
" 8/1 1.15150 \n",
" 9/1 1.19202 \n",
" 10/1 1.17677 \n",
" 11/1 1.20272 \n",
" 12/1 1.21366 1.20819 +/- 0.00547\n",
" 13/1 1.15906 1.19181 +/- 0.01668\n",
" 14/1 1.14687 1.18058 +/- 0.01629\n",
" 15/1 1.14570 1.17360 +/- 0.01442\n",
" 16/1 1.13480 1.16713 +/- 0.01343\n",
" 17/1 1.17680 1.16852 +/- 0.01144\n",
" 18/1 1.16866 1.16853 +/- 0.00990\n",
" 19/1 1.19253 1.17120 +/- 0.00913\n",
" 20/1 1.18124 1.17220 +/- 0.00823\n",
" 21/1 1.19206 1.17401 +/- 0.00766\n",
" 22/1 1.17681 1.17424 +/- 0.00700\n",
" 23/1 1.17634 1.17440 +/- 0.00644\n",
" 24/1 1.13659 1.17170 +/- 0.00654\n",
" 25/1 1.17144 1.17169 +/- 0.00609\n",
" 26/1 1.20649 1.17386 +/- 0.00610\n",
" 27/1 1.11238 1.17024 +/- 0.00678\n",
" 28/1 1.18911 1.17129 +/- 0.00647\n",
" 29/1 1.14681 1.17000 +/- 0.00626\n",
" 30/1 1.12152 1.16758 +/- 0.00641\n",
" 31/1 1.12729 1.16566 +/- 0.00639\n",
" 32/1 1.15399 1.16513 +/- 0.00612\n",
" 33/1 1.13547 1.16384 +/- 0.00599\n",
" 34/1 1.17723 1.16440 +/- 0.00576\n",
" 35/1 1.09296 1.16154 +/- 0.00622\n",
" 36/1 1.19621 1.16287 +/- 0.00612\n",
" 37/1 1.12560 1.16149 +/- 0.00605\n",
" 38/1 1.17872 1.16211 +/- 0.00586\n",
" 39/1 1.17721 1.16263 +/- 0.00568\n",
" 40/1 1.13724 1.16178 +/- 0.00555\n",
" 41/1 1.18526 1.16254 +/- 0.00542\n",
" 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",
" 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",
" 49/1 1.17938 1.16155 +/- 0.00468\n",
" 50/1 1.15798 1.16146 +/- 0.00457\n",
" Creating state point statepoint.50.h5...\n",
"\n",
" ===========================================================================\n",
@ -605,27 +606,27 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\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",
" Total time for initialization = 4.6200E-01 seconds\n",
" Reading cross sections = 1.3100E-01 seconds\n",
" Total time in simulation = 2.4000E+00 seconds\n",
" Time in transport only = 2.1340E+00 seconds\n",
" Time in inactive batches = 2.6400E-01 seconds\n",
" Time in active batches = 2.1360E+00 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",
" Time accumulating tallies = 0.0000E+00 seconds\n",
" Total time for finalization = 1.0000E-03 seconds\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",
" Total time elapsed = 2.8800E+00 seconds\n",
" Calculation Rate (inactive) = 94697.0 neutrons/second\n",
" Calculation Rate (active) = 46816.5 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
" k-effective (Collision) = 1.16131 +/- 0.00453\n",
" k-effective (Track-length) = 1.16206 +/- 0.00465\n",
" k-effective (Absorption) = 1.16096 +/- 0.00364\n",
" Combined k-effective = 1.16120 +/- 0.00325\n",
" k-effective (Collision) = 1.15984 +/- 0.00411\n",
" k-effective (Track-length) = 1.16146 +/- 0.00457\n",
" k-effective (Absorption) = 1.16177 +/- 0.00380\n",
" Combined k-effective = 1.16105 +/- 0.00364\n",
" Leakage Fraction = 0.00000 +/- 0.00000\n",
"\n"
]
@ -751,8 +752,8 @@
"\tDomain Type =\tcell\n",
"\tDomain ID =\t1\n",
"\tCross Sections [cm^-1]:\n",
" Group 1 [6.25e-07 - 20.0 MeV]:\t6.81e-01 +/- 1.88e-01%\n",
" Group 2 [0.0 - 6.25e-07 MeV]:\t1.40e+00 +/- 5.91e-01%\n",
" Group 1 [6.25e-07 - 20.0 MeV]:\t6.81e-01 +/- 2.69e-01%\n",
" Group 2 [0.0 - 6.25e-07 MeV]:\t1.40e+00 +/- 5.93e-01%\n",
"\n",
"\n",
"\n"
@ -780,7 +781,7 @@
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" <tr style=\"text-align: right;\">\n",
@ -795,19 +796,19 @@
" <tbody>\n",
" <tr>\n",
" <th>1</th>\n",
" <td> 1</td>\n",
" <td> 1</td>\n",
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" <td> 0.001264</td>\n",
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@ -815,8 +816,8 @@
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@ -891,7 +892,7 @@
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@ -908,23 +909,23 @@
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" <tr>\n",
" <th>0</th>\n",
" <td> 1</td>\n",
" <td> 0.000000</td>\n",
" <td> 0.000001</td>\n",
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" <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",
" <td>1</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>total</td>\n",
" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
" <td>-9.992007e-16</td>\n",
" <td>0.002570</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -935,9 +936,9 @@
"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... 4.88e-15 1.13e-02 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... 1.22e-15 1.80e-03 "
" score mean std. dev. \n",
"0 (((total / flux) - (absorption / flux)) - (sca... 8.88e-16 1.13e-02 \n",
"1 (((total / flux) - (absorption / flux)) - (sca... -9.99e-16 2.57e-03 "
]
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"execution_count": 23,
@ -970,7 +971,7 @@
{
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@ -987,23 +988,23 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\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",
" <td>1</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-07</td>\n",
" <td>total</td>\n",
" <td>((absorption / flux) / (total / flux))</td>\n",
" <td>0.076115</td>\n",
" <td>0.000649</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\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",
" <td>1</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>total</td>\n",
" <td>((absorption / flux) / (total / flux))</td>\n",
" <td>0.019263</td>\n",
" <td>0.000095</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1015,8 +1016,8 @@
"1 1 6.25e-07 2.00e+01 total \n",
"\n",
" 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 "
"0 ((absorption / flux) / (total / flux)) 7.61e-02 6.49e-04 \n",
"1 ((absorption / flux) / (total / flux)) 1.93e-02 9.46e-05 "
]
},
"execution_count": 24,
@ -1042,7 +1043,7 @@
{
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@ -1059,23 +1060,23 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\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",
" <td>1</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-07</td>\n",
" <td>total</td>\n",
" <td>((scatter / flux) / (total / flux))</td>\n",
" <td>0.923885</td>\n",
" <td>0.007736</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\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",
" <td>1</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>total</td>\n",
" <td>((scatter / flux) / (total / flux))</td>\n",
" <td>0.980737</td>\n",
" <td>0.003737</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1087,8 +1088,8 @@
"1 1 6.25e-07 2.00e+01 total \n",
"\n",
" 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 "
"0 ((scatter / flux) / (total / flux)) 9.24e-01 7.74e-03 \n",
"1 ((scatter / flux) / (total / flux)) 9.81e-01 3.74e-03 "
]
},
"execution_count": 25,
@ -1121,7 +1122,7 @@
{
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@ -1138,23 +1139,23 @@
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
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" <td> 0.007741</td>\n",
" <td>1</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-07</td>\n",
" <td>total</td>\n",
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" <tr>\n",
" <th>1</th>\n",
" <td> 1</td>\n",
" <td> 0.000001</td>\n",
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" <td> 1</td>\n",
" <td> 0.002619</td>\n",
" <td>1</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>total</td>\n",
" <td>(((absorption / flux) / (total / flux)) + ((sc...</td>\n",
" <td>1</td>\n",
" <td>0.003739</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1166,8 +1167,8 @@
"1 1 6.25e-07 2.00e+01 total \n",
"\n",
" 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 "
"0 (((absorption / flux) / (total / flux)) + ((sc... 1.00e+00 7.76e-03 \n",
"1 (((absorption / flux) / (total / flux)) + ((sc... 1.00e+00 3.74e-03 "
]
},
"execution_count": 26,
@ -1200,7 +1201,7 @@
"name": "python",
"nbconvert_exporter": "python",
"pygments_lexer": "ipython2",
"version": "2.7.10"
"version": "2.7.11"
}
},
"nbformat": 4,

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@ -366,7 +366,7 @@
"outputs": [
{
"data": {
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@ -570,8 +570,10 @@
" 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: b9efc990c7eb58f4a41524d59ae73396c9929436\n",
" Date/Time: 2016-02-23 10:52:44\n",
" Git SHA1: 5f252e2df51930b9175fd41bafa8db01f3eaeb92\n",
" Date/Time: 2016-03-23 14:50:46\n",
" MPI Processes: 1\n",
" OpenMP Threads: 16\n",
"\n",
" ===========================================================================\n",
" ========================> INITIALIZATION <=========================\n",
@ -598,26 +600,26 @@
"\n",
" Bat./Gen. k Average k \n",
" ========= ======== ==================== \n",
" 1/1 1.05992 \n",
" 2/1 1.05251 \n",
" 3/1 1.05204 \n",
" 4/1 1.02100 \n",
" 5/1 1.07784 \n",
" 6/1 1.04814 \n",
" 7/1 1.02335 1.03574 +/- 0.01239\n",
" 8/1 1.02415 1.03188 +/- 0.00813\n",
" 9/1 1.10331 1.04974 +/- 0.01876\n",
" 10/1 1.05452 1.05069 +/- 0.01456\n",
" 11/1 1.07867 1.05536 +/- 0.01277\n",
" 12/1 1.04203 1.05345 +/- 0.01096\n",
" 13/1 1.04482 1.05237 +/- 0.00955\n",
" 14/1 1.04117 1.05113 +/- 0.00852\n",
" 15/1 1.07581 1.05360 +/- 0.00801\n",
" 16/1 1.04235 1.05257 +/- 0.00731\n",
" 17/1 1.02710 1.05045 +/- 0.00701\n",
" 18/1 1.01970 1.04809 +/- 0.00687\n",
" 19/1 1.01022 1.04538 +/- 0.00691\n",
" 20/1 1.01449 1.04332 +/- 0.00675\n",
" 1/1 1.03167 \n",
" 2/1 1.03535 \n",
" 3/1 1.02709 \n",
" 4/1 1.00637 \n",
" 5/1 0.99250 \n",
" 6/1 1.06116 \n",
" 7/1 1.04289 1.05202 +/- 0.00913\n",
" 8/1 1.04779 1.05061 +/- 0.00546\n",
" 9/1 1.04695 1.04969 +/- 0.00397\n",
" 10/1 0.98778 1.03731 +/- 0.01276\n",
" 11/1 1.05810 1.04078 +/- 0.01098\n",
" 12/1 1.01539 1.03715 +/- 0.00996\n",
" 13/1 1.08644 1.04331 +/- 0.01060\n",
" 14/1 1.06425 1.04564 +/- 0.00963\n",
" 15/1 1.01768 1.04284 +/- 0.00906\n",
" 16/1 1.05877 1.04429 +/- 0.00832\n",
" 17/1 1.02195 1.04243 +/- 0.00782\n",
" 18/1 1.02488 1.04108 +/- 0.00732\n",
" 19/1 1.06285 1.04263 +/- 0.00695\n",
" 20/1 0.98751 1.03896 +/- 0.00744\n",
" Creating state point statepoint.20.h5...\n",
"\n",
" ===========================================================================\n",
@ -627,27 +629,27 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 8.4700E-01 seconds\n",
" Reading cross sections = 5.8300E-01 seconds\n",
" Total time in simulation = 1.6037E+01 seconds\n",
" Time in transport only = 1.6026E+01 seconds\n",
" Time in inactive batches = 2.3070E+00 seconds\n",
" Time in active batches = 1.3730E+01 seconds\n",
" Time synchronizing fission bank = 5.0000E-03 seconds\n",
" Sampling source sites = 4.0000E-03 seconds\n",
" Total time for initialization = 5.0400E-01 seconds\n",
" Reading cross sections = 1.5000E-01 seconds\n",
" Total time in simulation = 2.1570E+00 seconds\n",
" Time in transport only = 1.9760E+00 seconds\n",
" Time in inactive batches = 3.3600E-01 seconds\n",
" Time in active batches = 1.8210E+00 seconds\n",
" Time synchronizing fission bank = 4.0000E-03 seconds\n",
" Sampling source sites = 3.0000E-03 seconds\n",
" SEND/RECV source sites = 1.0000E-03 seconds\n",
" Time accumulating tallies = 0.0000E+00 seconds\n",
" Total time for finalization = 3.0000E-03 seconds\n",
" Total time elapsed = 1.6899E+01 seconds\n",
" Calculation Rate (inactive) = 5418.29 neutrons/second\n",
" Calculation Rate (active) = 2731.25 neutrons/second\n",
" Total time for finalization = 2.0000E-03 seconds\n",
" Total time elapsed = 2.6800E+00 seconds\n",
" Calculation Rate (inactive) = 37202.4 neutrons/second\n",
" Calculation Rate (active) = 20593.1 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
" k-effective (Collision) = 1.03935 +/- 0.00682\n",
" k-effective (Track-length) = 1.04332 +/- 0.00675\n",
" k-effective (Absorption) = 1.03845 +/- 0.00598\n",
" Combined k-effective = 1.04024 +/- 0.00523\n",
" k-effective (Collision) = 1.03965 +/- 0.00597\n",
" k-effective (Track-length) = 1.03896 +/- 0.00744\n",
" k-effective (Absorption) = 1.03976 +/- 0.00606\n",
" Combined k-effective = 1.03991 +/- 0.00536\n",
" Leakage Fraction = 0.00000 +/- 0.00000\n",
"\n"
]
@ -738,7 +740,7 @@
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@ -754,8 +756,8 @@
" <th>0</th>\n",
" <td>total</td>\n",
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" <td>1.040166</td>\n",
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@ -763,7 +765,7 @@
],
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" nuclide score mean std. dev.\n",
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"0 total (nu-fission / absorption) 1.04e+00 9.69e-03"
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},
"execution_count": 26,
@ -798,7 +800,7 @@
{
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],
"text/plain": [
" 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"
"0 0.00e+00 6.25e-07 total absorption 6.92e-01 7.22e-03"
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"execution_count": 27,
@ -860,7 +862,7 @@
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" <tr>\n",
" <th>0</th>\n",
" <td>0</td>\n",
" <td>0.000001</td>\n",
" <td>6.250000e-07</td>\n",
" <td>total</td>\n",
" <td>nu-fission</td>\n",
" <td>1.201216</td>\n",
" <td>0.012288</td>\n",
" <td>1.202298</td>\n",
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@ -889,7 +891,7 @@
],
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" 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"
"0 0.00e+00 6.25e-07 total nu-fission 1.20e+00 1.34e-02"
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},
"execution_count": 28,
@ -923,7 +925,7 @@
{
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"</table>\n",
@ -957,7 +959,7 @@
"0 0.00e+00 6.25e-07 10000 total absorption 7.49e-01 \n",
"\n",
" std. dev. \n",
"0 8.26e-03 "
"0 9.00e-03 "
]
},
"execution_count": 29,
@ -989,7 +991,7 @@
{
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@ -1007,12 +1009,12 @@
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" <td>0.018624</td>\n",
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@ -1023,7 +1025,7 @@
"0 0.00e+00 6.25e-07 10000 total \n",
"\n",
" score mean std. dev. \n",
"0 (nu-fission / absorption) 1.66e+00 1.86e-02 "
"0 (nu-fission / absorption) 1.66e+00 2.00e-02 "
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},
"execution_count": 30,
@ -1054,7 +1056,7 @@
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" <td>(((absorption * nu-fission) * absorption) * (n...</td>\n",
" <td>1.040166</td>\n",
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@ -1088,7 +1090,7 @@
"0 0.00e+00 6.25e-07 10000 total \n",
"\n",
" score mean std. dev. \n",
"0 (((absorption * nu-fission) * absorption) * (n... 1.04e+00 2.19e-02 "
"0 (((absorption * nu-fission) * absorption) * (n... 1.04e+00 2.37e-02 "
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@ -1136,7 +1138,7 @@
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" <td>(U-238 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>0.000001</td>\n",
" <td>7.377419e-09</td>\n",
" <td>6.627781e-07</td>\n",
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" <tr>\n",
" <th>1</th>\n",
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" <tr>\n",
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" <td>(scatter / flux)</td>\n",
" <td>0.003367</td>\n",
" <td>1.647058e-05</td>\n",
" <td>3.369592e-03</td>\n",
" <td>8.971220e-06</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1247,14 +1249,14 @@
"7 10000 6.25e-07 2.00e+01 (U-235 / total) \n",
"\n",
" 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 "
"0 (nu-fission / flux) 6.63e-07 7.08e-09 \n",
"1 (scatter / flux) 2.10e-01 2.00e-03 \n",
"2 (nu-fission / flux) 3.55e-01 3.85e-03 \n",
"3 (scatter / flux) 5.55e-03 5.32e-05 \n",
"4 (nu-fission / flux) 7.15e-03 5.48e-05 \n",
"5 (scatter / flux) 2.28e-01 6.42e-04 \n",
"6 (nu-fission / flux) 8.07e-03 4.37e-05 \n",
"7 (scatter / flux) 3.37e-03 8.97e-06 "
]
},
"execution_count": 33,
@ -1285,11 +1287,11 @@
"name": "stdout",
"output_type": "stream",
"text": [
"[[[ 6.65702880e-07]\n",
" [ 3.56420449e-01]]\n",
"[[[ 6.62778145e-07]\n",
" [ 3.54724568e-01]]\n",
"\n",
" [[ 7.15488656e-03]\n",
" [ 8.06673774e-03]]]\n"
" [[ 7.15116511e-03]\n",
" [ 8.07363630e-03]]]\n"
]
}
],
@ -1317,9 +1319,9 @@
"name": "stdout",
"output_type": "stream",
"text": [
"[[[ 0.00555533]]\n",
"[[[ 0.00555418]]\n",
"\n",
" [[ 0.0033668 ]]]\n"
" [[ 0.00336959]]]\n"
]
}
],
@ -1341,8 +1343,8 @@
"name": "stdout",
"output_type": "stream",
"text": [
"[[[ 0.22777006]\n",
" [ 0.0033668 ]]]\n"
"[[[ 0.22789806]\n",
" [ 0.00336959]]]\n"
]
}
],
@ -1371,7 +1373,7 @@
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<div>\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
@ -1389,42 +1391,42 @@
" <tr>\n",
" <th>0</th>\n",
" <td>10000</td>\n",
" <td>0.000000</td>\n",
" <td>0.000001</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-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>1.338459e-08</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>10000</td>\n",
" <td>0.000000</td>\n",
" <td>0.000001</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-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>0.864141</td>\n",
" <td>7.363278e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
" <td>10000</td>\n",
" <td>0.000001</td>\n",
" <td>20.000000</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+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>0.082111</td>\n",
" <td>6.090952e-04</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
" <td>10000</td>\n",
" <td>0.000001</td>\n",
" <td>20.000000</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+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>0.092703</td>\n",
" <td>4.695215e-04</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1432,16 +1434,16 @@
],
"text/plain": [
" 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",
"0 10000 0.00e+00 6.25e-07 U-238 nu-fission 1.61e-06 \n",
"1 10000 0.00e+00 6.25e-07 U-235 nu-fission 8.64e-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",
"3 10000 6.25e-07 2.00e+01 U-235 nu-fission 9.27e-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 "
"0 1.34e-08 \n",
"1 7.36e-03 \n",
"2 6.09e-04 \n",
"3 4.70e-04 "
]
},
"execution_count": 37,
@ -1465,7 +1467,7 @@
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<div>\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
@ -1484,91 +1486,91 @@
" <th>0</th>\n",
" <td>10002</td>\n",
" <td>1.000000e-08</td>\n",
" <td>0.000000</td>\n",
" <td>1.080060e-07</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>4.619398</td>\n",
" <td>0.040124</td>\n",
" <td>4.591022</td>\n",
" <td>0.043961</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>10002</td>\n",
" <td>1.080060e-07</td>\n",
" <td>0.000001</td>\n",
" <td>1.166529e-06</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.030757</td>\n",
" <td>0.011239</td>\n",
" <td>2.032481</td>\n",
" <td>0.010876</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
" <td>10002</td>\n",
" <td>1.166529e-06</td>\n",
" <td>0.000013</td>\n",
" <td>1.259921e-05</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>1.658488</td>\n",
" <td>0.009777</td>\n",
" <td>1.654187</td>\n",
" <td>0.012130</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
" <td>10002</td>\n",
" <td>1.259921e-05</td>\n",
" <td>0.000136</td>\n",
" <td>1.360790e-04</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>1.853002</td>\n",
" <td>0.007378</td>\n",
" <td>1.864771</td>\n",
" <td>0.011649</td>\n",
" </tr>\n",
" <tr>\n",
" <th>4</th>\n",
" <td>10002</td>\n",
" <td>1.360790e-04</td>\n",
" <td>0.001470</td>\n",
" <td>1.469734e-03</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.050773</td>\n",
" <td>0.012484</td>\n",
" <td>2.056893</td>\n",
" <td>0.008555</td>\n",
" </tr>\n",
" <tr>\n",
" <th>5</th>\n",
" <td>10002</td>\n",
" <td>1.469734e-03</td>\n",
" <td>0.015874</td>\n",
" <td>1.587401e-02</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.131759</td>\n",
" <td>0.007821</td>\n",
" <td>2.138833</td>\n",
" <td>0.015180</td>\n",
" </tr>\n",
" <tr>\n",
" <th>6</th>\n",
" <td>10002</td>\n",
" <td>1.587401e-02</td>\n",
" <td>0.171449</td>\n",
" <td>1.714488e-01</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.213710</td>\n",
" <td>0.015159</td>\n",
" <td>2.207209</td>\n",
" <td>0.014853</td>\n",
" </tr>\n",
" <tr>\n",
" <th>7</th>\n",
" <td>10002</td>\n",
" <td>1.714488e-01</td>\n",
" <td>1.851749</td>\n",
" <td>1.851749e+00</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.011925</td>\n",
" <td>0.009406</td>\n",
" <td>1.999407</td>\n",
" <td>0.009053</td>\n",
" </tr>\n",
" <tr>\n",
" <th>8</th>\n",
" <td>10002</td>\n",
" <td>1.851749e+00</td>\n",
" <td>20.000000</td>\n",
" <td>2.000000e+01</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>0.371280</td>\n",
" <td>0.003949</td>\n",
" <td>0.368760</td>\n",
" <td>0.003373</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
@ -1576,26 +1578,26 @@
],
"text/plain": [
" 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",
"0 10002 1.00e-08 1.08e-07 H-1 scatter 4.59e+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",
"2 10002 1.17e-06 1.26e-05 H-1 scatter 1.65e+00 \n",
"3 10002 1.26e-05 1.36e-04 H-1 scatter 1.86e+00 \n",
"4 10002 1.36e-04 1.47e-03 H-1 scatter 2.06e+00 \n",
"5 10002 1.47e-03 1.59e-02 H-1 scatter 2.14e+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",
"7 10002 1.71e-01 1.85e+00 H-1 scatter 2.00e+00 \n",
"8 10002 1.85e+00 2.00e+01 H-1 scatter 3.69e-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 "
"0 4.40e-02 \n",
"1 1.09e-02 \n",
"2 1.21e-02 \n",
"3 1.16e-02 \n",
"4 8.56e-03 \n",
"5 1.52e-02 \n",
"6 1.49e-02 \n",
"7 9.05e-03 \n",
"8 3.37e-03 "
]
},
"execution_count": 38,
@ -1607,7 +1609,7 @@
"# \"Slice\" the H-1 scatter data in the moderator Cell into a new derived Tally\n",
"need_to_slice = sp.get_tally(name='need-to-slice')\n",
"slice_test = need_to_slice.get_slice(scores=['scatter'], nuclides=['H-1'],\n",
" filters=['cell'], filter_bins=[(moderator_cell.id,)])\n",
" filters=['cell'], filter_bins=[(moderator_cell.id,)])\n",
"slice_test.get_pandas_dataframe()"
]
}
@ -1628,7 +1630,7 @@
"name": "python",
"nbconvert_exporter": "python",
"pygments_lexer": "ipython2",
"version": "2.7.10"
"version": "2.7.11"
}
},
"nbformat": 4,

3
docs/source/pythonapi/index.rst
View file

@ -19,6 +19,7 @@ on a given module or class.
:maxdepth: 1
ace
mgxs_library
**Creating input files:**
@ -65,8 +66,6 @@ on a given module or class.
:maxdepth: 1
mgxs
energy_groups
mgxs_library
**Example Jupyter Notebooks:**

57
docs/source/pythonapi/mgxs.rst
View file

@ -4,31 +4,57 @@
Multi-Group Cross Sections
==========================
.. currentmodule:: openmc.mgxs.mgxs
----------------------------
Summary of Available Classes
----------------------------
Energy Groups
-------------
.. currentmodule:: openmc.mgxs.groups
.. autosummary::
MGXS
AbsorptionXS
CaptureXS
Chi
FissionXS
NuFissionXS
NuScatterXS
NuScatterMatrixXS
ScatterXS
ScatterMatrixXS
TotalXS
TransportXS
EnergyGroups
Multi-group Cross Sections
--------------------------
.. currentmodule:: openmc.mgxs.mgxs
.. autosummary::
MGXS
AbsorptionXS
CaptureXS
Chi
FissionXS
NuFissionXS
NuScatterXS
NuScatterMatrixXS
ScatterXS
ScatterMatrixXS
TotalXS
TransportXS
Multi-group Cross Section Libraries
-----------------------------------
.. currentmodule:: openmc.mgxs.library
.. autosummary::
Library
-------------------
Class Documentation
-------------------
.. automodule:: openmc.mgxs.groups
:members:
.. currentmodule:: openmc.mgxs.mgxs
.. autoclass:: MGXS
:members:
@ -64,3 +90,6 @@ Class Documentation
.. autoclass:: TransportXS
:members:
.. automodule:: openmc.mgxs.library
:members:

8
docs/source/pythonapi/mgxs_library.rst
View file

@ -1,8 +1,8 @@
.. _pythonapi_mgxs_library:
============
MGXS Library
============
==============================
Multi-group Cross Section Data
==============================
.. automodule:: openmc.mgxs.library
.. automodule:: openmc.mgxs_library
:members:

68
docs/source/usersguide/output/statepoint.rst
View file

@ -248,7 +248,7 @@ if run_mode == 'k-eigenvalue':
Accumulated sum and sum-of-squares for each global tally. The compound type
has fields named ``sum`` and ``sum_sq``.
**tallies_present** (*int*)
**/tallies_present** (*int*)
Flag indicated if tallies are present in the file.
@ -260,3 +260,69 @@ if (run_mode == 'k-eigenvalue' and source_present > 0)
``wgt``, ``xyz``, ``uvw``, ``E``, ``g``, and ``delayed_group``, which
represent the weight, position, direction, energy, energy group, and
delayed_group of the source particle, respectively.
**/runtime/total initialization** (*double*)
Time (in seconds on the master process) spent reading inputs, allocating
arrays, etc.
**/runtime/reading cross sections** (*double*)
Time (in seconds on the master process) spent loading cross section
libraries (this is a subset of initialization).
**/runtime/simulation** (*double*)
Time (in seconds on the master process) spent between initialization and
finalization.
**/runtime/transport** (*double*)
Time (in seconds on the master process) spent transporting particles.
**/runtime/inactive batches** (*double*)
Time (in seconds on the master process) spent in the inactive batches
(including non-transport activities like communcating sites).
**/runtime/active batches** (*double*)
Time (in seconds on the master process) spent in the active batches
(including non-transport activities like communicating sites).
**/runtime/synchronizing fission bank** (*double*)
Time (in seconds on the master process) spent sampling source particles
from fission sites and communicating them to other processes for load
balancing.
**/runtime/sampling source sites** (*double*)
Time (in seconds on the master process) spent sampling source particles
from fission sites.
**/runtime/SEND-RECV source sites** (*double*)
Time (in seconds on the master process) spent communicating source sites
between processes for load balancing.
**/runtime/accumulating tallies** (*double*)
Time (in seconds on the master process) spent communicating tally results
and evaluating their statistics.
**/runtime/CMFD** (*double*)
Time (in seconds on the master process) spent evaluating CMFD.
**/runtime/CMFD building matrices** (*double*)
Time (in seconds on the master process) spent buliding CMFD matrices.
**/runtime/CMFD solving matrices** (*double*)
Time (in seconds on the master process) spent solving CMFD matrices.
**/runtime/total** (*double*)
Total time spent (in seconds on the master process) in the program.

7
docs/source/usersguide/output/summary.rst
View file

@ -297,6 +297,13 @@ The current revision of the summary file format is 1.
Filter offset (used for distribcell filter).
**/tallies/tally <uid>/filter <j>/paths** (*char[][]*)
The paths traversed through the CSG tree to reach each distribcell
instance (for 'distribcell' filters only). This consists of the integer
IDs for each universe, cell and lattice delimited by '->'. Each lattice
cell is specified by its (x,y) or (x,y,z) indices.
**/tallies/tally <uid>/filter <j>/n_bins** (*int*)
Number of bins for the j-th filter.

28
openmc/filter.py
View file

@ -45,6 +45,9 @@ class Filter(object):
stride : Integral
The number of filter, nuclide and score bins within each of this
filter's bins.
distribcell_paths : list of str
The paths traversed through the CSG tree to reach each distribcell
instance (for 'distribcell' filters only)
"""
@ -56,6 +59,7 @@ class Filter(object):
self._bins = None
self._mesh = None
self._stride = None
self._distribcell_paths = None
if type is not None:
self.type = type
@ -110,6 +114,7 @@ class Filter(object):
clone._num_bins = self.num_bins
clone._mesh = copy.deepcopy(self.mesh, memo)
clone._stride = self.stride
clone._distribcell_paths = copy.deepcopy(self.distribcell_paths)
memo[id(self)] = clone
@ -152,6 +157,10 @@ class Filter(object):
def stride(self):
return self._stride
@property
def distribcell_paths(self):
return self._distribcell_paths
@type.setter
def type(self, type):
if type is None:
@ -246,6 +255,11 @@ class Filter(object):
self._stride = stride
@distribcell_paths.setter
def distribcell_paths(self, distribcell_paths):
cv.check_iterable_type('distribcell_paths', distribcell_paths, str)
self._distribcell_paths = distribcell_paths
def can_merge(self, other):
"""Determine if filter can be merged with another.
@ -632,18 +646,10 @@ class Filter(object):
# offsets to OpenCG LocalCoords linked lists
offsets_to_coords = {}
# Use OpenCG to compute LocalCoords linked list for
# each region and store in dictionary
for region in range(num_regions):
for offset, path in enumerate(self.distribcell_paths):
region = opencg_geometry.get_region_from_path(path)
coords = opencg_geometry.find_region(region)
path = opencg.get_path(coords)
cell_id = path[-1]
# If this region is in Cell corresponding to the
# distribcell filter bin, store it in dictionary
if cell_id == self.bins[0]:
offset = openmc_geometry.get_cell_instance(path)
offsets_to_coords[offset] = coords
offsets_to_coords[offset] = coords
# Each distribcell offset is a DataFrame bin
# Unravel the paths into DataFrame columns

8
openmc/geometry.py
View file

@ -63,15 +63,19 @@ class Geometry(object):
"""
# Extract the cell id from the path
last_index = path.rfind('>')
cell_id = int(path[last_index+1:])
# Find the distribcell index of the cell.
cells = self.get_all_cells()
for cell in cells:
if cell.id == path[-1]:
if cell.id == cell_id:
distribcell_index = cell.distribcell_index
break
else:
raise RuntimeError('Could not find cell {} specified in a \
distribcell filter'.format(path[-1]))
distribcell filter'.format(cell_id))
# Return memoize'd offset if possible
if (path, distribcell_index) in self._offsets:

3
openmc/material.py
View file

@ -723,9 +723,8 @@ class MaterialsFile(object):
material.make_isotropic_in_lab()
def _create_material_subelements(self):
subelement = ET.SubElement(self._materials_file, "default_xs")
if self._default_xs is not None:
subelement = ET.SubElement(self._materials_file, "default_xs")
subelement.text = self._default_xs
for material in self._materials:

21
openmc/mgxs/mgxs.py
View file

@ -67,10 +67,6 @@ class MGXS(object):
The energy group structure for energy condensation
by_nuclide : bool
If true, computes cross sections for each nuclide in domain
nuclides : Iterable of basestring
The user-specified nuclides to compute cross sections. If by_nuclide
is True but nuclides are not specified by the user, all nuclides in the
spatial domain will be used.
name : str, optional
Name of the multi-group cross section. Used as a label to identify
tallies in OpenMC 'tallies.xml' file.
@ -109,9 +105,11 @@ class MGXS(object):
num_nuclides : Integral
The number of nuclides for which the multi-group cross section is
being tracked. This is unity if the by_nuclide attribute is False.
nuclides : list of str or 'sum'
A list of nuclide string names (e.g., 'U-238', 'O-16') when by_nuclide
is True and 'sum' when by_nuclide is False.
nuclides : Iterable of str or 'sum'
The optional user-specified nuclides for which to compute cross
sections (e.g., 'U-238', 'O-16'). If by_nuclide is True but nuclides
are not specified by the user, all nuclides in the spatial domain
are included. This attribute is 'sum' if by_nuclide is false.
sparse : bool
Whether or not the MGXS' tallies use SciPy's LIL sparse matrix format
for compressed data storage
@ -553,7 +551,7 @@ class MGXS(object):
# If this is a by-nuclide cross-section, add all nuclides to Tally
if self.by_nuclide and score != 'flux':
all_nuclides = self.domain.get_all_nuclides()
all_nuclides = self.get_all_nuclides()
for nuclide in all_nuclides:
self.tallies[key].nuclides.append(nuclide)
else:
@ -761,10 +759,9 @@ class MGXS(object):
# Reverse energies to align with increasing energy groups
xs = xs[:, ::-1, :]
# Eliminate trivial dimensions
xs = np.squeeze(xs)
xs = np.atleast_1d(xs)
# Eliminate trivial dimensions
xs = np.squeeze(xs)
xs = np.atleast_1d(xs)
return xs
def get_condensed_xs(self, coarse_groups):

95
openmc/mgxs_library.py
View file

@ -87,8 +87,9 @@ class XSdata(object):
----------
name : str, optional
Name of the mgxs data set.
representation : {'isotropic', 'angle'}
energy_groups : openmc.mgxs.EnergyGroups
Energygroup structure
representation : {'isotropic', 'angle'}, optional
Method used in generating the MGXS (isotropic or angle-dependent flux
weighting). Defaults to 'isotropic'
@ -99,10 +100,10 @@ class XSdata(object):
alias : str
Separate unique identifier for the xsdata object
kT : float
Temperature (in units of MeV) of this data set.
energy_groups : EnergyGroups
Temperature (in units of MeV).
energy_groups : openmc.mgxs.EnergyGroups
Energy group structure
fissionable : boolean
fissionable : bool
Whether or not this is a fissionable data set.
scatt_type : {'legendre', 'histogram', or 'tabular'}
Angular distribution representation (legendre, histogram, or tabular)
@ -115,6 +116,85 @@ class XSdata(object):
Legendre polynomial form). Dict contains two keys: 'enable' and
'num_points'. 'enable' is a boolean and 'num_points' is the
number of points to use, if 'enable' is True.
num_azimuthal : int
Number of equal width angular bins that the azimuthal angular domain is
subdivided into. This only applies when ``representation`` is "angle".
num_polar : int
Number of equal width angular bins that the polar angular domain is
subdivided into. This only applies when ``representation`` is "angle".
total : numpy.ndarray
Group-wise total cross section ordered by increasing group index (i.e.,
fast to thermal). If ``representation`` is "isotropic", then the length
of this list should equal the number of groups described in the
``groups`` element. If ``representation`` is "angle", then the length
of this list should equal the number of groups times the number of
azimuthal angles times the number of polar angles, with the
inner-dimension being groups, intermediate-dimension being azimuthal
angles and outer-dimension being the polar angles.
absorption : numpy.ndarray
Group-wise absorption cross section ordered by increasing group index
(i.e., fast to thermal). If ``representation`` is "isotropic", then the
length of this list should equal the number of groups described in the
``groups`` attribute. If ``representation`` is "angle", then the length
of this list should equal the number of groups times the number of
azimuthal angles times the number of polar angles, with the
inner-dimension being groups, intermediate-dimension being azimuthal
angles and outer-dimension being the polar angles.
scatter : numpy.ndarray
Scattering moment matrices presented with the columns representing
incoming group and rows representing the outgoing group. That is,
down-scatter will be above the diagonal of the resultant matrix. This
matrix is repeated for every Legendre order (in order of increasing
orders) if ``scatt_type`` is "legendre"; otherwise, this matrix is
repeated for every bin of the histogram or tabular representation.
Finally, if ``representation`` is "angle", the above is repeated for
every azimuthal angle and every polar angle, in that order.
multiplicity : numpy.ndarray
Ratio of neutrons produced in scattering collisions to the neutrons
which undergo scattering collisions; that is, the multiplicity provides
the code with a scaling factor to account for neutrons being produced in
(n,xn) reactions. This information is assumed isotropic and therefore
does not need to be repeated for every Legendre moment or
histogram/tabular bin. This matrix follows the same arrangement as
described for the ``scatter`` attribute, with the exception of the data
needed to provide the scattering type information.
fission : numpy.ndarray
Group-wise fission cross section ordered by increasing group index
(i.e., fast to thermal). If ``representation`` is "isotropic", then the
length of this list should equal the number of groups described in the
``groups`` attribute. If ``representation`` is "angle", then the length
of this list should equal the number of groups times the number of
azimuthal angles times the number of polar angles, with the
inner-dimension being groups, intermediate-dimension being azimuthal
angles and outer-dimension being the polar angles.
k_fission : numpy.ndarray
Group-wise kappa-fission cross section ordered by increasing group index
(i.e., fast to thermal). If ``representation`` is "isotropic", then the
length of this list should equal the number of groups described in the
``groups`` attribute. If ``representation`` is "angle", then the length
of this list should equal the number of groups times the number of
azimuthal angles times the number of polar angles, with the
inner-dimension being groups, intermediate-dimension being azimuthal
angles and outer-dimension being the polar angles.
chi : numpy.ndarray
Group-wise fission spectra ordered by increasing group index (i.e., fast
to thermal). This attribute should be used if making the common
approximation that the fission spectra does not depend on incoming
energy. If the user does not wish to make this approximation, then this
should not be provided and this information included in the
``nu_fission`` element instead. If ``representation`` is "isotropic",
then the length of this list should equal the number of groups described
in the ``groups`` element. If ``representation`` is "angle", then the
length of this list should equal the number of groups times the number
of azimuthal angles times the number of polar angles, with the
inner-dimension being groups, intermediate-dimension being azimuthal
angles and outer-dimension being the polar angles.
nu_fission : numpy.ndarray
Group-wise fission production cross section vector (i.e., if ``chi`` is
provided), or is the group-wise fission production matrix. If providing
the vector, it should be ordered the same as the ``fission`` data. If
providing the matrix, it should be ordered the same as the
``multiplicity`` matrix.
"""
def __init__(self, name, energy_groups, representation="isotropic"):
@ -577,8 +657,6 @@ class MGXSLibraryFile(object):
Energy group structure.
inverse_velocities : Iterable of Real
Inverse of velocities, units of sec/cm
filename : str
XML file to write to.
xsdatas : Iterable of XSdata
Iterable of multi-Group cross section data objects
"""
@ -717,6 +795,3 @@ class MGXSLibraryFile(object):
tree = ET.ElementTree(self._cross_sections_file)
tree.write(filename, xml_declaration=True,
encoding='utf-8', method="xml")

1
openmc/opencg_compatible.py
View file

@ -1002,6 +1002,7 @@ def get_opencg_geometry(openmc_geometry):
opencg_geometry = opencg.Geometry()
opencg_geometry.root_universe = opencg_root_universe
opencg_geometry.initialize_cell_offsets()
opencg_geometry.assign_auto_ids()
return opencg_geometry

23
openmc/statepoint.py
View file

@ -68,6 +68,9 @@ class StatePoint(object):
Working directory for simulation
run_mode : str
Simulation run mode, e.g. 'k-eigenvalue'
runtime : dict
Dictionary whose keys are strings describing various runtime metrics
and whose values are time values in seconds.
seed : Integral
Pseudorandom number generator seed
source : ndarray of compound datatype
@ -101,8 +104,9 @@ class StatePoint(object):
raise IOError('{} is not a statepoint file.'.format(filename))
except AttributeError:
raise IOError('Could not read statepoint file. This most likely '
'means the statepoint file was produced by a different '
'version of OpenMC than the one you are using.')
'means the statepoint file was produced by a '
'different version of OpenMC than the one you are '
'using.')
if self._f['revision'].value != 15:
raise IOError('Statepoint file has a file revision of {} '
'which is not consistent with the revision this '
@ -311,6 +315,11 @@ class StatePoint(object):
def run_mode(self):
return self._f['run_mode'].value.decode()
@property
def runtime(self):
return {name: dataset.value
for name, dataset in self._f['runtime'].items()}
@property
def seed(self):
return self._f['seed'].value
@ -609,11 +618,13 @@ class StatePoint(object):
raise ValueError(msg)
for tally_id, tally in self.tallies.items():
# Get the Tally name from the summary file
tally.name = summary.tallies[tally_id].name
summary_tally = summary.tallies[tally_id]
tally.name = summary_tally.name
tally.with_summary = True
for tally_filter in tally.filters:
summary_filter = summary_tally.find_filter(tally_filter.type)
if tally_filter.type == 'surface':
surface_ids = []
for bin in tally_filter.bins:
@ -626,6 +637,10 @@ class StatePoint(object):
distribcell_ids.append(summary.cells[bin].id)
tally_filter.bins = distribcell_ids
if tally_filter.type == 'distribcell':
tally_filter.distribcell_paths = \
summary_filter.distribcell_paths
if tally_filter.type == 'universe':
universe_ids = []
for bin in tally_filter.bins:

6
openmc/summary.py
View file

@ -565,6 +565,12 @@ class Summary(object):
new_filter = openmc.Filter(filter_type, bins)
new_filter.num_bins = num_bins
# Read in distribcell paths
if filter_type == 'distribcell':
paths = self._f['{0}/paths'.format(subsubbase)][...]
paths = [str(path.decode()) for path in paths]
new_filter.distribcell_paths = paths
# Add Filter to the Tally
tally.filters.append(new_filter)

7
openmc/trigger.py
View file

@ -2,8 +2,9 @@ from numbers import Real
from xml.etree import ElementTree as ET
import sys
import warnings
from collections import Iterable
from openmc.checkvalue import check_type, check_value
import openmc.checkvalue as cv
if sys.version_info[0] >= 3:
basestring = str
@ -87,13 +88,13 @@ class Trigger(object):
@trigger_type.setter
def trigger_type(self, trigger_type):
check_value('tally trigger type', trigger_type,
cv.check_value('tally trigger type', trigger_type,
['variance', 'std_dev', 'rel_err'])
self._trigger_type = trigger_type
@threshold.setter
def threshold(self, threshold):
check_type('tally trigger threshold', threshold, Real)
cv.check_type('tally trigger threshold', threshold, Real)
self._threshold = threshold
@scores.setter

43
openmc/universe.py
View file

@ -324,9 +324,6 @@ class Cell(object):
self.region = Intersection(self.region, region)
def get_cell_instance(self, path, distribcell_index):
# Get the current element and remove it from the list
cell_id = path[0]
path = path[1:]
# If the Cell is filled by a Material
if self._type == 'normal' or self._type == 'void':
@ -655,11 +652,19 @@ class Universe(object):
self._cells.clear()
def get_cell_instance(self, path, distribcell_index):
# Get the current element and remove it from the list
path = path[1:]
# Get the Cell ID
cell_id = path[0]
# Pop off the root Universe ID from the path
next_index = path.index('-')
path = path[next_index+2:]
# Extract the Cell ID from the path
if '-' in path:
next_index = path.index('-')
cell_id = int(path[:next_index])
path = path[next_index+2:]
else:
cell_id = int(path)
path = ''
# Make a recursive call to the Cell within this Universe
offset = self.cells[cell_id].get_cell_instance(path, distribcell_index)
@ -1123,20 +1128,30 @@ class RectLattice(Lattice):
self._pitch = pitch
def get_cell_instance(self, path, distribcell_index):
# Get the current element and remove it from the list
i = path[0]
path = path[1:]
# Extract the lattice element from the path
next_index = path.index('-')
lat_id_indices = path[:next_index]
path = path[next_index+2:]
# Extract the lattice cell indices from the path
i1 = lat_id_indices.index('(')
i2 = lat_id_indices.index(')')
i = lat_id_indices[i1+1:i2]
lat_x = int(i.split(',')[0]) - 1
lat_y = int(i.split(',')[1]) - 1
lat_z = int(i.split(',')[2]) - 1
# For 2D Lattices
if len(self._dimension) == 2:
offset = self._offsets[i[3]-1, i[2]-1, i[1]-1, distribcell_index-1]
offset += self._universes[i[1]-1][i[2]-1].get_cell_instance(path,
offset = self._offsets[lat_z, lat_y, lat_x, distribcell_index-1]
offset += self._universes[lat_x][lat_y].get_cell_instance(path,
distribcell_index)
# For 3D Lattices
else:
offset = self._offsets[i[3]-1, i[2]-1, i[1]-1, distribcell_index-1]
offset += self._universes[i[3]-1][i[2]-1][i[1]-1].get_cell_instance(
offset = self._offsets[lat_z, lat_y, lat_x, distribcell_index-1]
offset += self._universes[lat_z][lat_y][lat_x].get_cell_instance(
path, distribcell_index)
return offset

2
src/output.F90
View file

@ -1158,7 +1158,7 @@ contains
function get_label(t, i_filter) result(label)
type(TallyObject), intent(in) :: t ! tally object
integer, intent(in) :: i_filter ! index in filters array
character(100) :: label ! user-specified identifier
character(MAX_LINE_LEN) :: label ! user-specified identifier
integer :: i ! index in cells/surfaces/etc array
integer :: bin

147
src/state_point.F90
View file

@ -49,10 +49,8 @@ contains
integer, allocatable :: id_array(:)
integer, allocatable :: key_array(:)
integer(HID_T) :: file_id
integer(HID_T) :: cmfd_group
integer(HID_T) :: tallies_group, tally_group
integer(HID_T) :: meshes_group, mesh_group
integer(HID_T) :: filter_group
integer(HID_T) :: cmfd_group, tallies_group, tally_group, meshes_group, &
mesh_group, filter_group, runtime_group
character(20), allocatable :: str_array(:)
character(MAX_FILE_LEN) :: filename
type(RegularMesh), pointer :: meshp
@ -133,13 +131,13 @@ contains
call write_dataset(file_id, "cmfd_on", 1)
cmfd_group = create_group(file_id, "cmfd")
call write_dataset(cmfd_group, "indices", cmfd%indices)
call write_dataset(cmfd_group, "k_cmfd", cmfd%k_cmfd)
call write_dataset(cmfd_group, "cmfd_src", cmfd%cmfd_src)
call write_dataset(cmfd_group, "cmfd_entropy", cmfd%entropy)
call write_dataset(cmfd_group, "cmfd_balance", cmfd%balance)
call write_dataset(cmfd_group, "cmfd_dominance", cmfd%dom)
call write_dataset(cmfd_group, "cmfd_srccmp", cmfd%src_cmp)
call write_dataset(cmfd_group, "indices", cmfd % indices)
call write_dataset(cmfd_group, "k_cmfd", cmfd % k_cmfd)
call write_dataset(cmfd_group, "cmfd_src", cmfd % cmfd_src)
call write_dataset(cmfd_group, "cmfd_entropy", cmfd % entropy)
call write_dataset(cmfd_group, "cmfd_balance", cmfd % balance)
call write_dataset(cmfd_group, "cmfd_dominance", cmfd % dom)
call write_dataset(cmfd_group, "cmfd_srccmp", cmfd % src_cmp)
call close_group(cmfd_group)
else
call write_dataset(file_id, "cmfd_on", 0)
@ -155,18 +153,18 @@ contains
if (n_meshes > 0) then
! Print list of mesh IDs
current => mesh_dict%keys()
current => mesh_dict % keys()
allocate(id_array(n_meshes))
allocate(key_array(n_meshes))
i = 1
do while (associated(current))
key_array(i) = current%key
id_array(i) = current%value
key_array(i) = current % key
id_array(i) = current % value
! Move to next mesh
next => current%next
next => current % next
deallocate(current)
current => next
i = i + 1
@ -180,16 +178,17 @@ contains
! Write information for meshes
MESH_LOOP: do i = 1, n_meshes
meshp => meshes(id_array(i))
mesh_group = create_group(meshes_group, "mesh " // trim(to_str(meshp%id)))
mesh_group = create_group(meshes_group, "mesh " &
// trim(to_str(meshp % id)))
select case (meshp%type)
select case (meshp % type)
case (MESH_REGULAR)
call write_dataset(mesh_group, "type", "regular")
end select
call write_dataset(mesh_group, "dimension", meshp%dimension)
call write_dataset(mesh_group, "lower_left", meshp%lower_left)
call write_dataset(mesh_group, "upper_right", meshp%upper_right)
call write_dataset(mesh_group, "width", meshp%width)
call write_dataset(mesh_group, "dimension", meshp % dimension)
call write_dataset(mesh_group, "lower_left", meshp % lower_left)
call write_dataset(mesh_group, "upper_right", meshp % upper_right)
call write_dataset(mesh_group, "width", meshp % width)
call close_group(mesh_group)
end do MESH_LOOP
@ -211,7 +210,7 @@ contains
! Write all tally information except results
do i = 1, n_tallies
tally => tallies(i)
key_array(i) = tally%id
key_array(i) = tally % id
id_array(i) = i
end do
@ -226,9 +225,9 @@ contains
! Get pointer to tally
tally => tallies(i)
tally_group = create_group(tallies_group, "tally " // &
trim(to_str(tally%id)))
trim(to_str(tally % id)))
select case(tally%estimator)
select case(tally % estimator)
case (ESTIMATOR_ANALOG)
call write_dataset(tally_group, "estimator", "analog")
case (ESTIMATOR_TRACKLENGTH)
@ -236,16 +235,17 @@ contains
case (ESTIMATOR_COLLISION)
call write_dataset(tally_group, "estimator", "collision")
end select
call write_dataset(tally_group, "n_realizations", tally%n_realizations)
call write_dataset(tally_group, "n_filters", tally%n_filters)
call write_dataset(tally_group, "n_realizations", &
tally % n_realizations)
call write_dataset(tally_group, "n_filters", tally % n_filters)
! Write filter information
FILTER_LOOP: do j = 1, tally%n_filters
FILTER_LOOP: do j = 1, tally % n_filters
filter_group = create_group(tally_group, "filter " // &
trim(to_str(j)))
! Write name of type
select case (tally%filters(j)%type)
select case (tally % filters(j) % type)
case(FILTER_UNIVERSE)
call write_dataset(filter_group, "type", "universe")
case(FILTER_MATERIAL)
@ -274,36 +274,37 @@ contains
call write_dataset(filter_group, "type", "delayedgroup")
end select
call write_dataset(filter_group, "n_bins", tally%filters(j)%n_bins)
call write_dataset(filter_group, "n_bins", &
tally % filters(j) % n_bins)
if (tally % filters(j) % type == FILTER_ENERGYIN .or. &
tally % filters(j) % type == FILTER_ENERGYOUT .or. &
tally % filters(j) % type == FILTER_MU .or. &
tally % filters(j) % type == FILTER_POLAR .or. &
tally % filters(j) % type == FILTER_AZIMUTHAL) then
call write_dataset(filter_group, "bins", &
tally%filters(j)%real_bins)
tally % filters(j) % real_bins)
else
call write_dataset(filter_group, "bins", &
tally%filters(j)%int_bins)
tally % filters(j) % int_bins)
end if
call close_group(filter_group)
end do FILTER_LOOP
! Set up nuclide bin array and then write
allocate(str_array(tally%n_nuclide_bins))
NUCLIDE_LOOP: do j = 1, tally%n_nuclide_bins
if (tally%nuclide_bins(j) > 0) then
allocate(str_array(tally % n_nuclide_bins))
NUCLIDE_LOOP: do j = 1, tally % n_nuclide_bins
if (tally % nuclide_bins(j) > 0) then
! Get index in cross section listings for this nuclide
i_list = nuclides(tally%nuclide_bins(j))%listing
i_list = nuclides(tally % nuclide_bins(j)) % listing
! Determine position of . in alias string (e.g. "U-235.71c"). If
! no . is found, just use the entire string.
i_xs = index(xs_listings(i_list)%alias, '.')
i_xs = index(xs_listings(i_list) % alias, '.')
if (i_xs > 0) then
str_array(j) = xs_listings(i_list)%alias(1:i_xs - 1)
str_array(j) = xs_listings(i_list) % alias(1:i_xs - 1)
else
str_array(j) = xs_listings(i_list)%alias
str_array(j) = xs_listings(i_list) % alias
end if
else
str_array(j) = 'total'
@ -312,32 +313,33 @@ contains
call write_dataset(tally_group, "nuclides", str_array)
deallocate(str_array)
call write_dataset(tally_group, "n_score_bins", tally%n_score_bins)
allocate(str_array(size(tally%score_bins)))
do j = 1, size(tally%score_bins)
str_array(j) = reaction_name(tally%score_bins(j))
call write_dataset(tally_group, "n_score_bins", tally % n_score_bins)
allocate(str_array(size(tally % score_bins)))
do j = 1, size(tally % score_bins)
str_array(j) = reaction_name(tally % score_bins(j))
end do
call write_dataset(tally_group, "score_bins", str_array)
call write_dataset(tally_group, "n_user_score_bins", tally%n_user_score_bins)
call write_dataset(tally_group, "n_user_score_bins", &
tally % n_user_score_bins)
deallocate(str_array)
! Write explicit moment order strings for each score bin
k = 1
allocate(str_array(tally%n_score_bins))
MOMENT_LOOP: do j = 1, tally%n_user_score_bins
select case(tally%score_bins(k))
allocate(str_array(tally % n_score_bins))
MOMENT_LOOP: do j = 1, tally % n_user_score_bins
select case(tally % score_bins(k))
case (SCORE_SCATTER_N, SCORE_NU_SCATTER_N)
str_array(k) = 'P' // trim(to_str(tally%moment_order(k)))
str_array(k) = 'P' // trim(to_str(tally % moment_order(k)))
k = k + 1
case (SCORE_SCATTER_PN, SCORE_NU_SCATTER_PN)
do n_order = 0, tally%moment_order(k)
do n_order = 0, tally % moment_order(k)
str_array(k) = 'P' // trim(to_str(n_order))
k = k + 1
end do
case (SCORE_SCATTER_YN, SCORE_NU_SCATTER_YN, SCORE_FLUX_YN, &
SCORE_TOTAL_YN)
do n_order = 0, tally%moment_order(k)
do n_order = 0, tally % moment_order(k)
do nm_order = -n_order, n_order
str_array(k) = 'Y' // trim(to_str(n_order)) // ',' // &
trim(to_str(nm_order))
@ -389,8 +391,9 @@ contains
tally => tallies(i)
! Write sum and sum_sq for each bin
tally_group = open_group(tallies_group, "tally " // to_str(tally%id))
call write_dataset(tally_group, "results", tally%results)
tally_group = open_group(tallies_group, "tally " &
// to_str(tally % id))
call write_dataset(tally_group, "results", tally % results)
call close_group(tally_group)
end do TALLY_RESULTS
@ -400,13 +403,45 @@ contains
end if
call close_group(tallies_group)
! Write out the runtime metrics.
runtime_group = create_group(file_id, "runtime")
call write_dataset(runtime_group, "total initialization", &
time_initialize % get_value())
call write_dataset(runtime_group, "reading cross sections", &
time_read_xs % get_value())
call write_dataset(runtime_group, "simulation", &
time_inactive % get_value() + time_active % get_value())
call write_dataset(runtime_group, "transport", &
time_transport % get_value())
if (run_mode == MODE_EIGENVALUE) then
call write_dataset(runtime_group, "inactive batches", &
time_inactive % get_value())
end if
call write_dataset(runtime_group, "active batches", &
time_active % get_value())
if (run_mode == MODE_EIGENVALUE) then
call write_dataset(runtime_group, "synchronizing fission bank", &
time_bank % get_value())
call write_dataset(runtime_group, "sampling source sites", &
time_bank_sample % get_value())
call write_dataset(runtime_group, "SEND-RECV source sites", &
time_bank_sendrecv % get_value())
end if
call write_dataset(runtime_group, "accumulating tallies", &
time_tallies % get_value())
if (cmfd_run) then
call write_dataset(runtime_group, "CMFD", time_cmfd % get_value())
call write_dataset(runtime_group, "CMFD building matrices", &
time_cmfdbuild % get_value())
call write_dataset(runtime_group, "CMFD solving matrices", &
time_cmfdsolve % get_value())
end if
call write_dataset(runtime_group, "total", time_total % get_value())
call close_group(runtime_group)
call file_close(file_id)
end if
if (master .and. n_tallies > 0) then
deallocate(id_array)
end if
end subroutine write_state_point
!===============================================================================

103
src/summary.F90
View file

@ -3,7 +3,7 @@ module summary
use constants
use endf, only: reaction_name
use geometry_header, only: Cell, Universe, Lattice, RectLattice, &
&HexLattice
&HexLattice, BASE_UNIVERSE
use global
use hdf5_interface
use material_header, only: Material
@ -13,6 +13,7 @@ module summary
use surface_header
use string, only: to_str
use tally_header, only: TallyObject
use output, only: find_offset
use hdf5
@ -541,6 +542,10 @@ contains
type(RegularMesh), pointer :: m
type(TallyObject), pointer :: t
integer :: offset ! distibcell offset
character(MAX_LINE_LEN), allocatable :: paths(:) ! distribcell paths array
character(MAX_LINE_LEN) :: path ! distribcell path
tallies_group = create_group(file_id, "tallies")
! Write total number of meshes
@ -583,21 +588,40 @@ contains
! Write number of filters
call write_dataset(tally_group, "n_filters", t%n_filters)
FILTER_LOOP: do j = 1, t%n_filters
FILTER_LOOP: do j = 1, t % n_filters
filter_group = create_group(tally_group, "filter " // trim(to_str(j)))
! Write number of bins for this filter
call write_dataset(filter_group, "n_bins", t%filters(j)%n_bins)
call write_dataset(filter_group, "n_bins", t % filters(j) % n_bins)
! Write filter bins
if (t%filters(j)%type == FILTER_ENERGYIN .or. &
t%filters(j)%type == FILTER_ENERGYOUT .or. &
t%filters(j)%type == FILTER_MU .or. &
t%filters(j)%type == FILTER_POLAR .or. &
t%filters(j)%type == FILTER_AZIMUTHAL) then
call write_dataset(filter_group, "bins", t%filters(j)%real_bins)
if (t % filters(j) % type == FILTER_ENERGYIN .or. &
t % filters(j)% type == FILTER_ENERGYOUT .or. &
t % filters(j) % type == FILTER_MU .or. &
t % filters(j) % type == FILTER_POLAR .or. &
t % filters(j) % type == FILTER_AZIMUTHAL) then
call write_dataset(filter_group, "bins", t % filters(j) % real_bins)
else
call write_dataset(filter_group, "bins", t%filters(j)%int_bins)
call write_dataset(filter_group, "bins", t % filters(j) % int_bins)
end if
! Write paths to reach each distribcell instance
if (t % filters(j) % type == FILTER_DISTRIBCELL) then
! Allocate array of strings for each distribcell path
allocate(paths(t % filters(j) % n_bins))
! Store path for each distribcell instance
do k = 1, t % filters(j) % n_bins
path = ''
offset = 1
call find_offset(t % filters(j) % int_bins(1), &
universes(BASE_UNIVERSE), k, offset, path)
paths(k) = path
end do
! Write array of distribcell paths to summary file
call write_dataset(filter_group, "paths", paths)
deallocate(paths)
end if
! Write name of type
@ -701,63 +725,4 @@ contains
end subroutine write_tallies
!===============================================================================
! WRITE_TIMING
!===============================================================================
subroutine write_timing(file_id)
integer(HID_T), intent(in) :: file_id
integer(8) :: total_particles
integer(HID_T) :: time_group
real(8) :: speed
time_group = create_group(file_id, "timing")
! Write timing data
call write_dataset(time_group, "time_initialize", time_initialize%elapsed)
call write_dataset(time_group, "time_read_xs", time_read_xs%elapsed)
call write_dataset(time_group, "time_transport", time_transport%elapsed)
call write_dataset(time_group, "time_bank", time_bank%elapsed)
call write_dataset(time_group, "time_bank_sample", time_bank_sample%elapsed)
call write_dataset(time_group, "time_bank_sendrecv", time_bank_sendrecv%elapsed)
call write_dataset(time_group, "time_tallies", time_tallies%elapsed)
call write_dataset(time_group, "time_inactive", time_inactive%elapsed)
call write_dataset(time_group, "time_active", time_active%elapsed)
call write_dataset(time_group, "time_finalize", time_finalize%elapsed)
call write_dataset(time_group, "time_total", time_total%elapsed)
! Add descriptions to timing data
call write_attribute_string(time_group, "time_initialize", "description", &
"Total time elapsed for initialization (s)")
call write_attribute_string(time_group, "time_read_xs", "description", &
"Time reading cross-section libraries (s)")
call write_attribute_string(time_group, "time_transport", "description", &
"Time in transport only (s)")
call write_attribute_string(time_group, "time_bank", "description", &
"Total time synchronizing fission bank (s)")
call write_attribute_string(time_group, "time_bank_sample", "description", &
"Time between generations sampling source sites (s)")
call write_attribute_string(time_group, "time_bank_sendrecv", "description", &
"Time between generations SEND/RECVing source sites (s)")
call write_attribute_string(time_group, "time_tallies", "description", &
"Time between batches accumulating tallies (s)")
call write_attribute_string(time_group, "time_inactive", "description", &
"Total time in inactive batches (s)")
call write_attribute_string(time_group, "time_active", "description", &
"Total time in active batches (s)")
call write_attribute_string(time_group, "time_finalize", "description", &
"Total time for finalization (s)")
call write_attribute_string(time_group, "time_total", "description", &
"Total time elapsed (s)")
! Write calculation rate
total_particles = n_particles * n_batches * gen_per_batch
speed = real(total_particles) / (time_inactive%elapsed + &
time_active%elapsed)
call write_dataset(time_group, "neutrons_per_second", speed)
call close_group(time_group)
end subroutine write_timing
end module summary

6
tests/run_tests.py
View file

@ -363,10 +363,14 @@ sourcepoint_batch|statepoint_interval|survival_biasing|\
tally_assumesep|translation|uniform_fs|universe|void"
# Delete items of dictionary if valgrind or coverage and not in script mode
to_delete = []
if not script_mode:
for key in tests:
if re.search('valgrind|coverage', key):
del tests[key]
to_delete.append(key)
for key in to_delete:
del tests[key]
# Check if tests empty
if len(list(tests.keys())) == 0:

2
tests/test_source/inputs_true.dat
View file

@ -1 +1 @@
5c2fdde85affcd44c1b02c07c300acb8e5c189c1adbf7aa079e37a68e8b8313678fc292bd7f6e0d0957f723e05b8146bd165cf3315dde5f6b2f88ebc954cd65e
526c91551d9a80dc01216e5cb04162253f12ec684cc2b4912ca18cfc510f1ea2e5303029f1c1607882082b0c2c8a47f25dd5be14678f449a1579e3601d1bdec5