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https://github.com/openmc-dev/openmc.git
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merged with new-mgxs-tallies branch
This commit is contained in:
commit
16e74656b0
19 changed files with 734 additions and 803 deletions
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@ -384,7 +384,7 @@
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"* `NuScatterMatrixXS`\n",
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"* `Chi`\n",
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"* `ChiPrompt`\n",
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"* `Velocity`\n",
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"* `InverseVelocity`\n",
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"* `PromptNuFissionXS`\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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@ -432,26 +432,16 @@
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" \tID =\t10000\n",
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" \tName =\t\n",
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" \tFilters =\t\n",
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<<<<<<< HEAD
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" \t\tmesh\t[10000]\n",
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" \t\tenergy\t[0.000000E+00 6.250000E-07 2.000000E+01]\n",
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=======
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" \t\tcell\t[1]\n",
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" \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n",
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>>>>>>> upstream/develop
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" \tNuclides =\ttotal \n",
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" \tScores =\t['flux']\n",
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" \tEstimator =\ttracklength), ('absorption', Tally\n",
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" \tID =\t10001\n",
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" \tName =\t\n",
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" \tFilters =\t\n",
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<<<<<<< HEAD
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" \t\tmesh\t[10000]\n",
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" \t\tenergy\t[0.000000E+00 6.250000E-07 2.000000E+01]\n",
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=======
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" \t\tcell\t[1]\n",
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" \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n",
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>>>>>>> upstream/develop
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" \tNuclides =\ttotal \n",
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" \tScores =\t['absorption']\n",
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" \tEstimator =\ttracklength)])"
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@ -531,14 +521,8 @@
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" Copyright: 2011-2016 Massachusetts Institute of Technology\n",
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" License: http://openmc.readthedocs.io/en/latest/license.html\n",
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" Version: 0.7.1\n",
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<<<<<<< HEAD
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" Git SHA1: 6a66fb9af7372435dc7da987c8fc3d6acff6549a\n",
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" Date/Time: 2016-07-07 16:43:21\n",
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" MPI Processes: 1\n",
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=======
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" Git SHA1: 3d68c07625e33cd64188df03ee03e9c31b3d4b74\n",
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" Date/Time: 2016-07-22 21:03:18\n",
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>>>>>>> upstream/develop
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"\n",
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" ===========================================================================\n",
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" ========================> INITIALIZATION <=========================\n",
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@ -623,22 +607,6 @@
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"\n",
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" =======================> TIMING STATISTICS <=======================\n",
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"\n",
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<<<<<<< HEAD
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" Total time for initialization = 7.1900E-01 seconds\n",
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" Reading cross sections = 2.0400E-01 seconds\n",
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" Total time in simulation = 2.4932E+01 seconds\n",
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" Time in transport only = 2.4916E+01 seconds\n",
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" Time in inactive batches = 2.1830E+00 seconds\n",
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" Time in active batches = 2.2749E+01 seconds\n",
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" Time synchronizing fission bank = 4.0000E-03 seconds\n",
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" Sampling source sites = 4.0000E-03 seconds\n",
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" SEND/RECV source sites = 0.0000E+00 seconds\n",
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" Time accumulating tallies = 1.0000E-03 seconds\n",
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" Total time for finalization = 2.0000E-03 seconds\n",
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" Total time elapsed = 2.5667E+01 seconds\n",
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" Calculation Rate (inactive) = 11452.1 neutrons/second\n",
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" Calculation Rate (active) = 4395.80 neutrons/second\n",
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=======
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" Total time for initialization = 3.2300E-01 seconds\n",
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" Reading cross sections = 1.6900E-01 seconds\n",
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" Total time in simulation = 1.9882E+01 seconds\n",
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@ -653,7 +621,6 @@
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" Total time elapsed = 2.0217E+01 seconds\n",
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" Calculation Rate (inactive) = 9402.03 neutrons/second\n",
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" Calculation Rate (active) = 5806.19 neutrons/second\n",
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>>>>>>> upstream/develop
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"\n",
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" ============================> RESULTS <============================\n",
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"\n",
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@ -1702,26 +1669,21 @@
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],
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"metadata": {
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"kernelspec": {
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"display_name": "Python 3",
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"display_name": "Python 2",
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"language": "python",
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"name": "python3"
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"name": "python2"
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},
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"language_info": {
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"codemirror_mode": {
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"name": "ipython",
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"version": 3
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"version": 2
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},
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"file_extension": ".py",
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"mimetype": "text/x-python",
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"name": "python",
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"nbconvert_exporter": "python",
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<<<<<<< HEAD
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"pygments_lexer": "ipython2",
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"version": "2.7.11"
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=======
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"pygments_lexer": "ipython3",
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"version": "3.5.2"
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>>>>>>> upstream/develop
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}
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},
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"nbformat": 4,
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@ -550,7 +550,7 @@
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"* `NuScatterMatrixXS` (`\"nu-scatter matrix\"`)\n",
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"* `Chi` (`\"chi\"`)\n",
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"* `ChiPrompt` (`\"chi prompt\"`)\n",
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"* `Velocity` (`\"velocity\"`)\n",
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"* `InverseVelocity` (`\"inverse-velocity\"`)\n",
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"* `PromptNuFissionXS` (`\"prompt-nu-fission\"`)\n",
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"\n",
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"In this case, let's create the multi-group cross sections needed to run an OpenMOC simulation to verify the accuracy of our cross sections. In particular, we will define `\"transport\"`, `\"nu-fission\"`, `'\"fission\"`, `\"nu-scatter matrix\"` and `\"chi\"` cross sections for our `Library`.\n",
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