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https://github.com/openmc-dev/openmc.git
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Update examples
This commit is contained in:
Sterling Harper
parent
57371d217a
commit
7419cd26b3
15 changed files with 639 additions and 554 deletions
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@ -338,7 +338,7 @@
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"outputs": [
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{
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"data": {
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||||
"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\nGaOiDwAAAABJRU5ErkJggg==\n",
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"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN\nAAB6JgAAgIQAAPoAAACA6AAAdTAAAOpgAAA6mAAAF3CculE8AAAADFBMVEX///9yEhLpgJFNv8Tq\nQYT7AAAAAWJLR0QAiAUdSAAAAAd0SU1FB+AJFRQqB1pnJtkAAALKSURBVGje7dpLcqQwDAbgHHE2\nYeEj+D4cwQucBUfo+3CEXoSp8OhuhF70T4qpKXmdr21LogK2Pj7A8QmNP+HDhw8fPnz48Kf6VH9G\n+66vy+je8k19jnf8C5dXIPv86ms56lPdjvaYbyodx3ze+XLE76cXFiD4zPji99z0/AJ4n1lfvJ6f\nnl0A6x+578efMSg1wPr172/jPO5yFXM+Ef78gdblM+WPHyguP//t1/g6pA0wfln+ho/fwgYYn19C\n/xwDvwHGc9OvC+hs37DTrwuwfWanXxdQTC9Mvyygs3wjTL8uwPJpn/tNDbSGz7T0SBEWw4vLXzbQ\n6b6RoveIoO6TvPxlA63qs7z8ZQPF9F+SH22vbX8OQKf5Rtv+EgDNJ3X58wZaxWd1+fMGiuFvir8b\nvjp8J/tGy/6jAmRvhW8fwL3vVT+o3grfPoB7r/IpALI3tz8FoJN84/NV873hB8UnM3xzANtf8nb4\ndwmg3grfFEDJO8JPE0i9Ff4pAYL3pI8mkHor/HMCeO9JH00g9SafEsh7T/ppARBvp48UwJnelT5S\nACd7O31TAlnvKx9SQCd7B58KgPO+8iMFuPWe9E8F8BveWX7bAjzX9y4//Jve+fhsH6Ctv7n8PTzj\nvY/v9gEOHz58+PBX+6v/f/wPvnd54f3j6venE/yl769Xv7+j3x/o98/V32/o9+fl389Xnx+g5x/o\n+Qt6/oOeP6HnX+j5G3z+h54/ouefV5/foufP6Pk3ev4On/+j9w/o/Qd6/4Le/6D3T/D9V67Y/ZsV\nQBq+s+8f0ftP+P41axXguP9NWgDuu/Cdfv+N3r/D9/9TAID+A7T/Ae2/gPs/0P4TtP8F7r9J3AIO\n9P+g/Udw/9Oygbf7r9D+L7j/DO1/Q/vv4P4/tP8Q7n9E+y/h/k+0/xTuf4X7b+H+X7T/+BPuf3aM\n8OHDhw8fPnz4w/4vzcvgeY10sY0AAAAldEVYdGRhdGU6Y3JlYXRlADIwMTYtMDktMjFUMTY6NDI6\nMDctMDQ6MDC5xU4UAAAAJXRFWHRkYXRlOm1vZGlmeQAyMDE2LTA5LTIxVDE2OjQyOjA3LTA0OjAw\nyJj2qAAAAABJRU5ErkJggg==\n",
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"text/plain": [
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"<IPython.core.display.Image object>"
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]
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@ -386,18 +386,18 @@
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"# Create Tallies to compute microscopic multi-group cross-sections\n",
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"\n",
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"# Instantiate energy filter for multi-group cross-section Tallies\n",
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"energy_filter = openmc.Filter(type='energy', bins=[0., 0.625e-6, 20.])\n",
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"energy_filter = openmc.EnergyFilter([0., 0.625e-6, 20.])\n",
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"\n",
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"# Instantiate flux Tally in moderator and fuel\n",
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"tally = openmc.Tally(name='flux')\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id, moderator_cell.id])]\n",
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"tally.filters = [openmc.CellFilter([fuel_cell.id, moderator_cell.id])]\n",
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"tally.filters.append(energy_filter)\n",
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"tally.scores = ['flux']\n",
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"tallies_file.append(tally)\n",
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"\n",
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"# Instantiate reaction rate Tally in fuel\n",
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"tally = openmc.Tally(name='fuel rxn rates')\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id])]\n",
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"tally.filters = [openmc.CellFilter([fuel_cell.id])]\n",
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"tally.filters.append(energy_filter)\n",
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"tally.scores = ['nu-fission', 'scatter']\n",
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"tally.nuclides = [u238, u235]\n",
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@ -405,7 +405,7 @@
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"\n",
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"# Instantiate reaction rate Tally in moderator\n",
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"tally = openmc.Tally(name='moderator rxn rates')\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[moderator_cell.id])]\n",
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"tally.filters = [openmc.CellFilter([moderator_cell.id])]\n",
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"tally.filters.append(energy_filter)\n",
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"tally.scores = ['absorption', 'total']\n",
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"tally.nuclides = [o16, h1]\n",
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@ -417,7 +417,7 @@
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"mesh.dimension = [1, 1, 1]\n",
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"mesh.lower_left = [-0.63, -0.63, -100.]\n",
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"mesh.width = [1.26, 1.26, 200.]\n",
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"mesh_filter = openmc.Filter(type='mesh', bins=[mesh.id])\n",
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"mesh_filter = openmc.MeshFilter(mesh.id)\n",
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"mesh_filter.mesh = mesh\n",
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"\n",
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"# Instantiate thermal, fast, and total leakage tallies\n",
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@ -427,12 +427,12 @@
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"tallies_file.append(leak)\n",
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"\n",
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"thermal_leak = openmc.Tally(name='thermal leakage')\n",
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"thermal_leak.filters = [mesh_filter, openmc.Filter(type='energy', bins=[0., 0.625e-6])]\n",
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"thermal_leak.filters = [mesh_filter, openmc.EnergyFilter([0., 0.625e-6])]\n",
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"thermal_leak.scores = ['current']\n",
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"tallies_file.append(thermal_leak)\n",
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"\n",
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"fast_leak = openmc.Tally(name='fast leakage')\n",
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"fast_leak.filters = [mesh_filter, openmc.Filter(type='energy', bins=[0.625e-6, 20.])]\n",
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"fast_leak.filters = [mesh_filter, openmc.EnergyFilter([0.625e-6, 20.])]\n",
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"fast_leak.scores = ['current']\n",
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"tallies_file.append(fast_leak)"
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]
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@ -464,7 +464,7 @@
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"# Resonance Escape Probability tallies\n",
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"therm_abs_rate = openmc.Tally(name='therm. abs. rate')\n",
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"therm_abs_rate.scores = ['absorption']\n",
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"therm_abs_rate.filters = [openmc.Filter(type='energy', bins=[0., 0.625e-6])]\n",
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"therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625e-6])]\n",
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"tallies_file.append(therm_abs_rate)"
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]
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},
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@ -479,8 +479,8 @@
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"# Thermal Flux Utilization tallies\n",
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"fuel_therm_abs_rate = openmc.Tally(name='fuel therm. abs. rate')\n",
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"fuel_therm_abs_rate.scores = ['absorption']\n",
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"fuel_therm_abs_rate.filters = [openmc.Filter(type='energy', bins=[0., 0.625e-6]),\n",
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" openmc.Filter(type='cell', bins=[fuel_cell.id])]\n",
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"fuel_therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625e-6]),\n",
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" openmc.CellFilter([fuel_cell.id])]\n",
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"tallies_file.append(fuel_therm_abs_rate)"
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]
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},
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@ -495,7 +495,7 @@
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"# Fast Fission Factor tallies\n",
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"therm_fiss_rate = openmc.Tally(name='therm. fiss. rate')\n",
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"therm_fiss_rate.scores = ['nu-fission']\n",
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"therm_fiss_rate.filters = [openmc.Filter(type='energy', bins=[0., 0.625e-6])]\n",
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"therm_fiss_rate.filters = [openmc.EnergyFilter([0., 0.625e-6])]\n",
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"tallies_file.append(therm_fiss_rate)"
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]
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},
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@ -508,11 +508,11 @@
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"outputs": [],
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"source": [
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"# Instantiate energy filter to illustrate Tally slicing\n",
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"fine_energy_filter = openmc.Filter(type='energy', bins=np.logspace(np.log10(1e-8), np.log10(20), 10))\n",
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"fine_energy_filter = openmc.EnergyFilter(np.logspace(np.log10(1e-8), np.log10(20), 10))\n",
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"\n",
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"# Instantiate flux Tally in moderator and fuel\n",
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"tally = openmc.Tally(name='need-to-slice')\n",
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"tally.filters = [openmc.Filter(type='cell', bins=[fuel_cell.id, moderator_cell.id])]\n",
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"tally.filters = [openmc.CellFilter(bins=[fuel_cell.id, moderator_cell.id])]\n",
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"tally.filters.append(fine_energy_filter)\n",
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"tally.scores = ['nu-fission', 'scatter']\n",
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"tally.nuclides = [h1, u238]\n",
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@ -550,7 +550,6 @@
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"name": "stdout",
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"output_type": "stream",
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"text": [
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"rm: cannot remove 'statepoint.*': No such file or directory\n",
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"\n",
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" %%%%%%%%%%%%%%%\n",
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" %%%%%%%%%%%%%%%%%%%%%%%%\n",
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@ -580,9 +579,9 @@
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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 | 0.8.0\n",
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" Git SHA1 | 623b705a399f16c8e5063732bc6e6a357611542d\n",
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" Date/Time | 2016-09-03 04:38:41\n",
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" OpenMP Threads | 4\n",
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" Git SHA1 | 57371d217a270b4013af4e33ca20b0053654b190\n",
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" Date/Time | 2016-09-21 16:42:14\n",
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" MPI Processes | 1\n",
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"\n",
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" ===========================================================================\n",
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" ========================> INITIALIZATION <=========================\n",
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@ -592,12 +591,12 @@
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" Reading geometry XML file...\n",
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" Reading cross sections XML file...\n",
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" Reading materials XML file...\n",
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" Reading U235 from /opt/xsdata/nndc_new/U235.h5\n",
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" Reading U238 from /opt/xsdata/nndc_new/U238.h5\n",
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" Reading O16 from /opt/xsdata/nndc_new/O16.h5\n",
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" Reading H1 from /opt/xsdata/nndc_new/H1.h5\n",
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" Reading B10 from /opt/xsdata/nndc_new/B10.h5\n",
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" Reading Zr90 from /opt/xsdata/nndc_new/Zr90.h5\n",
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" Reading U235 from /home/smharper/openmc/data/nndc_hdf5/U235.h5\n",
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" Reading U238 from /home/smharper/openmc/data/nndc_hdf5/U238.h5\n",
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" Reading O16 from /home/smharper/openmc/data/nndc_hdf5/O16.h5\n",
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" Reading H1 from /home/smharper/openmc/data/nndc_hdf5/H1.h5\n",
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" Reading B10 from /home/smharper/openmc/data/nndc_hdf5/B10.h5\n",
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" Reading Zr90 from /home/smharper/openmc/data/nndc_hdf5/Zr90.h5\n",
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" Maximum neutron transport energy: 20.0000 MeV for U235\n",
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" Reading tallies XML file...\n",
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" Building neighboring cells lists for each surface...\n",
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@ -638,20 +637,20 @@
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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 = 3.8900E-01 seconds\n",
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" Reading cross sections = 2.7000E-01 seconds\n",
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" Total time in simulation = 4.6960E+00 seconds\n",
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" Time in transport only = 4.6760E+00 seconds\n",
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" Time in inactive batches = 6.6400E-01 seconds\n",
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" Time in active batches = 4.0320E+00 seconds\n",
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" Time synchronizing fission bank = 1.0000E-03 seconds\n",
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" Sampling source sites = 1.0000E-03 seconds\n",
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" SEND/RECV source sites = 0.0000E+00 seconds\n",
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" Time accumulating tallies = 0.0000E+00 seconds\n",
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" Total time for finalization = 1.0000E-03 seconds\n",
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" Total time elapsed = 5.0960E+00 seconds\n",
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" Calculation Rate (inactive) = 18825.3 neutrons/second\n",
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" Calculation Rate (active) = 9300.60 neutrons/second\n",
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" Total time for initialization = 2.8800E-01 seconds\n",
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" Reading cross sections = 1.6900E-01 seconds\n",
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" Total time in simulation = 1.5410E+01 seconds\n",
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" Time in transport only = 1.5395E+01 seconds\n",
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" Time in inactive batches = 2.3750E+00 seconds\n",
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" Time in active batches = 1.3035E+01 seconds\n",
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" Time synchronizing fission bank = 4.0000E-03 seconds\n",
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" Sampling source sites = 2.0000E-03 seconds\n",
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" SEND/RECV source sites = 2.0000E-03 seconds\n",
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" Time accumulating tallies = 1.0000E-03 seconds\n",
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" Total time for finalization = 3.0000E-03 seconds\n",
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" Total time elapsed = 1.5718E+01 seconds\n",
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" Calculation Rate (inactive) = 5263.16 neutrons/second\n",
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" Calculation Rate (active) = 2876.87 neutrons/second\n",
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"\n",
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" ============================> RESULTS <============================\n",
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"\n",
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@ -768,8 +767,8 @@
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"\n",
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"# Get the leakage tally\n",
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"leak = sp.get_tally(name='leakage')\n",
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"leak = leak.summation(filter_type='surface', remove_filter=True)\n",
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"leak = leak.summation(filter_type='mesh', remove_filter=True)\n",
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"leak = leak.summation(filter_type=openmc.SurfaceFilter, remove_filter=True)\n",
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"leak = leak.summation(filter_type=openmc.MeshFilter, remove_filter=True)\n",
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"\n",
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"# Compute k-infinity using tally arithmetic\n",
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"keff = fiss_rate / (abs_rate + leak)\n",
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@ -839,8 +838,8 @@
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"# Compute resonance escape probability using tally arithmetic\n",
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"therm_abs_rate = sp.get_tally(name='therm. abs. rate')\n",
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"thermal_leak = sp.get_tally(name='thermal leakage')\n",
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"thermal_leak = thermal_leak.summation(filter_type='surface', remove_filter=True)\n",
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"thermal_leak = thermal_leak.summation(filter_type='mesh', remove_filter=True)\n",
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"thermal_leak = thermal_leak.summation(filter_type=openmc.SurfaceFilter, remove_filter=True)\n",
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"thermal_leak = thermal_leak.summation(filter_type=openmc.MeshFilter, remove_filter=True)\n",
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"res_esc = (therm_abs_rate + thermal_leak) / (abs_rate + thermal_leak)\n",
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"res_esc.get_pandas_dataframe()"
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]
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@ -1248,7 +1247,7 @@
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"source": [
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"# Compute microscopic multi-group cross-sections\n",
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"flux = sp.get_tally(name='flux')\n",
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"flux = flux.get_slice(filters=['cell'], filter_bins=[(fuel_cell.id,)])\n",
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"flux = flux.get_slice(filters=[openmc.CellFilter], filter_bins=[(fuel_cell.id,)])\n",
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"fuel_rxn_rates = sp.get_tally(name='fuel rxn rates')\n",
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"mod_rxn_rates = sp.get_tally(name='moderator rxn rates')"
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]
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@ -1475,7 +1474,7 @@
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],
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"source": [
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"# Show how to use Tally.get_values(...) with a CrossFilter and CrossScore\n",
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"fast_scatter_xs = fuel_xs.get_values(filters=['energy'], \n",
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"fast_scatter_xs = fuel_xs.get_values(filters=[openmc.EnergyFilter], \n",
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" filter_bins=[((0.625e-6, 20.),)], \n",
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" scores=['(scatter / flux)'])\n",
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"print(fast_scatter_xs)"
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@ -1734,9 +1733,18 @@
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"# \"Slice\" the H-1 scatter data in the moderator Cell into a new derived Tally\n",
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"need_to_slice = sp.get_tally(name='need-to-slice')\n",
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"slice_test = need_to_slice.get_slice(scores=['scatter'], nuclides=['H1'],\n",
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" filters=['cell'], filter_bins=[(moderator_cell.id,)])\n",
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" filters=[openmc.CellFilter], filter_bins=[(moderator_cell.id,)])\n",
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"slice_test.get_pandas_dataframe()"
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]
|
||||
},
|
||||
{
|
||||
"cell_type": "code",
|
||||
"execution_count": null,
|
||||
"metadata": {
|
||||
"collapsed": true
|
||||
},
|
||||
"outputs": [],
|
||||
"source": []
|
||||
}
|
||||
],
|
||||
"metadata": {
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue