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Respond to @smharper comments on #684

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This commit is contained in:
Paul Romano 2016-07-25 06:33:37 -05:00
parent 8952865c09
commit e2112b86ae
16 changed files with 1183 additions and 1185 deletions
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95
docs/source/pythonapi/examples/mgxs-part-i.ipynb
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@ -165,11 +165,11 @@
"outputs": [],
"source": [
"# Instantiate some Nuclides\n",
"h1 = openmc.Nuclide('H-1')\n",
"o16 = openmc.Nuclide('O-16')\n",
"u235 = openmc.Nuclide('U-235')\n",
"u238 = openmc.Nuclide('U-238')\n",
"zr90 = openmc.Nuclide('Zr-90')"
"h1 = openmc.Nuclide('H1')\n",
"o16 = openmc.Nuclide('O16')\n",
"u235 = openmc.Nuclide('U235')\n",
"u238 = openmc.Nuclide('U238')\n",
"zr90 = openmc.Nuclide('Zr90')"
]
},
{
@ -419,24 +419,22 @@
"data": {
"text/plain": [
"OrderedDict([('flux', Tally\n",
"\tID =\t10000\n",
"\tName =\t\n",
"\tFilters =\t\n",
" \t\tcell\t[1]\n",
" \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n",
"\tNuclides =\ttotal \n",
"\tScores =\t['flux']\n",
"\tEstimator =\ttracklength\n",
"), ('absorption', Tally\n",
"\tID =\t10001\n",
"\tName =\t\n",
"\tFilters =\t\n",
" \t\tcell\t[1]\n",
" \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n",
"\tNuclides =\ttotal \n",
"\tScores =\t['absorption']\n",
"\tEstimator =\ttracklength\n",
")])"
" \tID =\t10000\n",
" \tName =\t\n",
" \tFilters =\t\n",
" \t\tcell\t[1]\n",
" \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n",
" \tNuclides =\ttotal \n",
" \tScores =\t['flux']\n",
" \tEstimator =\ttracklength), ('absorption', Tally\n",
" \tID =\t10001\n",
" \tName =\t\n",
" \tFilters =\t\n",
" \t\tcell\t[1]\n",
" \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n",
" \tNuclides =\ttotal \n",
" \tScores =\t['absorption']\n",
" \tEstimator =\ttracklength)])"
]
},
"execution_count": 13,
@ -513,26 +511,25 @@
" Copyright: 2011-2016 Massachusetts Institute of Technology\n",
" License: http://openmc.readthedocs.io/en/latest/license.html\n",
" Version: 0.7.1\n",
" Git SHA1: 19feb55e6d5e8350398627f39fb55ee8e2e63011\n",
" Date/Time: 2016-05-13 10:19:16\n",
" MPI Processes: 1\n",
" Git SHA1: 3d68c07625e33cd64188df03ee03e9c31b3d4b74\n",
" Date/Time: 2016-07-22 21:03:18\n",
"\n",
" ===========================================================================\n",
" ========================> INITIALIZATION <=========================\n",
" ===========================================================================\n",
"\n",
" Reading settings XML file...\n",
" Reading cross sections XML file...\n",
" Reading geometry XML file...\n",
" Reading cross sections XML file...\n",
" Reading materials XML file...\n",
" Reading H1.71c from /home/romano/openmc/data/nndc_hdf5/H1_71c.h5\n",
" Reading O16.71c from /home/romano/openmc/data/nndc_hdf5/O16_71c.h5\n",
" Reading U235.71c from /home/romano/openmc/data/nndc_hdf5/U235_71c.h5\n",
" Reading U238.71c from /home/romano/openmc/data/nndc_hdf5/U238_71c.h5\n",
" Reading Zr90.71c from /home/romano/openmc/data/nndc_hdf5/Zr90_71c.h5\n",
" Maximum neutron transport energy: 20.0000 MeV for H1.71c\n",
" Reading tallies XML file...\n",
" Building neighboring cells lists for each surface...\n",
" Loading ACE cross section table: 1001.71c\n",
" Loading ACE cross section table: 8016.71c\n",
" Loading ACE cross section table: 92235.71c\n",
" Loading ACE cross section table: 92238.71c\n",
" Loading ACE cross section table: 40090.71c\n",
" Maximum neutron transport energy: 20.0000 MeV for 1001.71c\n",
" Initializing source particles...\n",
"\n",
" ===========================================================================\n",
@ -600,20 +597,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 4.2300E-01 seconds\n",
" Reading cross sections = 9.3000E-02 seconds\n",
" Total time in simulation = 1.6549E+01 seconds\n",
" Time in transport only = 1.6535E+01 seconds\n",
" Time in inactive batches = 2.3650E+00 seconds\n",
" Time in active batches = 1.4184E+01 seconds\n",
" Time synchronizing fission bank = 5.0000E-03 seconds\n",
" Sampling source sites = 3.0000E-03 seconds\n",
" Total time for initialization = 3.2300E-01 seconds\n",
" Reading cross sections = 1.6900E-01 seconds\n",
" Total time in simulation = 1.9882E+01 seconds\n",
" Time in transport only = 1.9869E+01 seconds\n",
" Time in inactive batches = 2.6590E+00 seconds\n",
" Time in active batches = 1.7223E+01 seconds\n",
" Time synchronizing fission bank = 4.0000E-03 seconds\n",
" Sampling source sites = 4.0000E-03 seconds\n",
" SEND/RECV source sites = 0.0000E+00 seconds\n",
" Time accumulating tallies = 0.0000E+00 seconds\n",
" Total time for finalization = 0.0000E+00 seconds\n",
" Total time elapsed = 1.6981E+01 seconds\n",
" Calculation Rate (inactive) = 10570.8 neutrons/second\n",
" Calculation Rate (active) = 7050.20 neutrons/second\n",
" Total time elapsed = 2.0217E+01 seconds\n",
" Calculation Rate (inactive) = 9402.03 neutrons/second\n",
" Calculation Rate (active) = 5806.19 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
@ -1167,21 +1164,21 @@
],
"metadata": {
"kernelspec": {
"display_name": "Python 2",
"display_name": "Python 3",
"language": "python",
"name": "python2"
"name": "python3"
},
"language_info": {
"codemirror_mode": {
"name": "ipython",
"version": 2
"version": 3
},
"file_extension": ".py",
"mimetype": "text/x-python",
"name": "python",
"nbconvert_exporter": "python",
"pygments_lexer": "ipython2",
"version": "2.7.6"
"pygments_lexer": "ipython3",
"version": "3.5.2"
}
},
"nbformat": 4,

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docs/source/pythonapi/examples/mgxs-part-ii.ipynb
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docs/source/pythonapi/examples/mgxs-part-iii.ipynb
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docs/source/pythonapi/examples/tally-arithmetic.ipynb
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@ -45,12 +45,12 @@
"outputs": [],
"source": [
"# Instantiate some Nuclides\n",
"h1 = openmc.Nuclide('H-1')\n",
"b10 = openmc.Nuclide('B-10')\n",
"o16 = openmc.Nuclide('O-16')\n",
"u235 = openmc.Nuclide('U-235')\n",
"u238 = openmc.Nuclide('U-238')\n",
"zr90 = openmc.Nuclide('Zr-90')"
"h1 = openmc.Nuclide('H1')\n",
"b10 = openmc.Nuclide('B10')\n",
"o16 = openmc.Nuclide('O16')\n",
"u235 = openmc.Nuclide('U235')\n",
"u238 = openmc.Nuclide('U238')\n",
"zr90 = openmc.Nuclide('Zr90')"
]
},
{
@ -339,7 +339,7 @@
"outputs": [
{
"data": {
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"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAACBjSFJN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\nP2X7EAAAAABJRU5ErkJggg==\n",
"text/plain": [
"<IPython.core.display.Image object>"
]
@ -540,28 +540,28 @@
" 888\n",
"\n",
" Copyright: 2011-2016 Massachusetts Institute of Technology\n",
" License: http://openmc.readthedocs.org/en/latest/license.html\n",
" License: http://openmc.readthedocs.io/en/latest/license.html\n",
" Version: 0.7.1\n",
" Git SHA1: df280b60eb1c6d7b7f842e05ede734a4883a0fc8\n",
" Date/Time: 2016-05-05 14:51:45\n",
" Git SHA1: 3d68c07625e33cd64188df03ee03e9c31b3d4b74\n",
" Date/Time: 2016-07-22 21:39:46\n",
"\n",
" ===========================================================================\n",
" ========================> INITIALIZATION <=========================\n",
" ===========================================================================\n",
"\n",
" Reading settings XML file...\n",
" Reading cross sections XML file...\n",
" Reading geometry XML file...\n",
" Reading cross sections XML file...\n",
" Reading materials XML file...\n",
" Reading U235.71c from /home/romano/openmc/data/nndc_hdf5/U235_71c.h5\n",
" Reading U238.71c from /home/romano/openmc/data/nndc_hdf5/U238_71c.h5\n",
" Reading O16.71c from /home/romano/openmc/data/nndc_hdf5/O16_71c.h5\n",
" Reading H1.71c from /home/romano/openmc/data/nndc_hdf5/H1_71c.h5\n",
" Reading B10.71c from /home/romano/openmc/data/nndc_hdf5/B10_71c.h5\n",
" Reading Zr90.71c from /home/romano/openmc/data/nndc_hdf5/Zr90_71c.h5\n",
" Maximum neutron transport energy: 20.0000 MeV for U235.71c\n",
" Reading tallies XML file...\n",
" Building neighboring cells lists for each surface...\n",
" Loading ACE cross section table: 92235.71c\n",
" Loading ACE cross section table: 92238.71c\n",
" Loading ACE cross section table: 8016.71c\n",
" Loading ACE cross section table: 1001.71c\n",
" Loading ACE cross section table: 5010.71c\n",
" Loading ACE cross section table: 40090.71c\n",
" Maximum neutron transport energy: 20.0000 MeV for 92235.71c\n",
" Initializing source particles...\n",
"\n",
" ===========================================================================\n",
@ -599,20 +599,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 7.2500E-01 seconds\n",
" Reading cross sections = 4.4400E-01 seconds\n",
" Total time in simulation = 1.5547E+01 seconds\n",
" Time in transport only = 1.5527E+01 seconds\n",
" Time in inactive batches = 2.2880E+00 seconds\n",
" Time in active batches = 1.3259E+01 seconds\n",
" Total time for initialization = 3.5600E-01 seconds\n",
" Reading cross sections = 2.3400E-01 seconds\n",
" Total time in simulation = 1.8333E+01 seconds\n",
" Time in transport only = 1.8325E+01 seconds\n",
" Time in inactive batches = 2.6950E+00 seconds\n",
" Time in active batches = 1.5638E+01 seconds\n",
" Time synchronizing fission bank = 1.0000E-03 seconds\n",
" Sampling source sites = 0.0000E+00 seconds\n",
" SEND/RECV source sites = 0.0000E+00 seconds\n",
" Time accumulating tallies = 1.0000E-03 seconds\n",
" Total time for finalization = 2.0000E-03 seconds\n",
" Total time elapsed = 1.6291E+01 seconds\n",
" Calculation Rate (inactive) = 5463.29 neutrons/second\n",
" Calculation Rate (active) = 2828.27 neutrons/second\n",
" SEND/RECV source sites = 1.0000E-03 seconds\n",
" Time accumulating tallies = 0.0000E+00 seconds\n",
" Total time for finalization = 1.0000E-03 seconds\n",
" Total time elapsed = 1.8711E+01 seconds\n",
" Calculation Rate (inactive) = 4638.22 neutrons/second\n",
" Calculation Rate (active) = 2398.00 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
@ -1107,7 +1107,7 @@
" <td>10000</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-07</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(U238 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>6.636968e-07</td>\n",
" <td>4.132875e-09</td>\n",
@ -1117,7 +1117,7 @@
" <td>10000</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-07</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(U238 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>2.099856e-01</td>\n",
" <td>1.232455e-03</td>\n",
@ -1127,7 +1127,7 @@
" <td>10000</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-07</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(U235 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>3.552458e-01</td>\n",
" <td>2.252681e-03</td>\n",
@ -1137,7 +1137,7 @@
" <td>10000</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-07</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(U235 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>5.554345e-03</td>\n",
" <td>3.265385e-05</td>\n",
@ -1147,7 +1147,7 @@
" <td>10000</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(U238 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>7.126668e-03</td>\n",
" <td>5.296883e-05</td>\n",
@ -1157,7 +1157,7 @@
" <td>10000</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(U238 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>2.277460e-01</td>\n",
" <td>1.003558e-03</td>\n",
@ -1167,7 +1167,7 @@
" <td>10000</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(U235 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>8.010911e-03</td>\n",
" <td>6.802256e-05</td>\n",
@ -1177,7 +1177,7 @@
" <td>10000</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(U235 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>3.367794e-03</td>\n",
" <td>1.443644e-05</td>\n",
@ -1187,15 +1187,15 @@
"</div>"
],
"text/plain": [
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
"0 10000 0.00e+00 6.25e-07 (U-238 / total) \n",
"1 10000 0.00e+00 6.25e-07 (U-238 / total) \n",
"2 10000 0.00e+00 6.25e-07 (U-235 / total) \n",
"3 10000 0.00e+00 6.25e-07 (U-235 / total) \n",
"4 10000 6.25e-07 2.00e+01 (U-238 / total) \n",
"5 10000 6.25e-07 2.00e+01 (U-238 / total) \n",
"6 10000 6.25e-07 2.00e+01 (U-235 / total) \n",
"7 10000 6.25e-07 2.00e+01 (U-235 / total) \n",
" cell energy low [MeV] energy high [MeV] nuclide \\\n",
"0 10000 0.00e+00 6.25e-07 (U238 / total) \n",
"1 10000 0.00e+00 6.25e-07 (U238 / total) \n",
"2 10000 0.00e+00 6.25e-07 (U235 / total) \n",
"3 10000 0.00e+00 6.25e-07 (U235 / total) \n",
"4 10000 6.25e-07 2.00e+01 (U238 / total) \n",
"5 10000 6.25e-07 2.00e+01 (U238 / total) \n",
"6 10000 6.25e-07 2.00e+01 (U235 / total) \n",
"7 10000 6.25e-07 2.00e+01 (U235 / total) \n",
"\n",
" score mean std. dev. \n",
"0 (nu-fission / flux) 6.64e-07 4.13e-09 \n",
@ -1276,7 +1276,7 @@
],
"source": [
"# Show how to use Tally.get_values(...) with a CrossScore and CrossNuclide\n",
"u235_scatter_xs = fuel_xs.get_values(nuclides=['(U-235 / total)'], \n",
"u235_scatter_xs = fuel_xs.get_values(nuclides=['(U235 / total)'], \n",
" scores=['(scatter / flux)'])\n",
"print(u235_scatter_xs)"
]
@ -1342,7 +1342,7 @@
" <td>10000</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-07</td>\n",
" <td>U-238</td>\n",
" <td>U238</td>\n",
" <td>nu-fission</td>\n",
" <td>0.000002</td>\n",
" <td>7.473789e-09</td>\n",
@ -1352,7 +1352,7 @@
" <td>10000</td>\n",
" <td>0.000000e+00</td>\n",
" <td>6.250000e-07</td>\n",
" <td>U-235</td>\n",
" <td>U235</td>\n",
" <td>nu-fission</td>\n",
" <td>0.861547</td>\n",
" <td>4.131310e-03</td>\n",
@ -1362,7 +1362,7 @@
" <td>10000</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>U-238</td>\n",
" <td>U238</td>\n",
" <td>nu-fission</td>\n",
" <td>0.082356</td>\n",
" <td>5.560461e-04</td>\n",
@ -1372,7 +1372,7 @@
" <td>10000</td>\n",
" <td>6.250000e-07</td>\n",
" <td>2.000000e+01</td>\n",
" <td>U-235</td>\n",
" <td>U235</td>\n",
" <td>nu-fission</td>\n",
" <td>0.092574</td>\n",
" <td>7.315442e-04</td>\n",
@ -1383,10 +1383,10 @@
],
"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 1.61e-06 \n",
"1 10000 0.00e+00 6.25e-07 U-235 nu-fission 8.62e-01 \n",
"2 10000 6.25e-07 2.00e+01 U-238 nu-fission 8.24e-02 \n",
"3 10000 6.25e-07 2.00e+01 U-235 nu-fission 9.26e-02 \n",
"0 10000 0.00e+00 6.25e-07 U238 nu-fission 1.61e-06 \n",
"1 10000 0.00e+00 6.25e-07 U235 nu-fission 8.62e-01 \n",
"2 10000 6.25e-07 2.00e+01 U238 nu-fission 8.24e-02 \n",
"3 10000 6.25e-07 2.00e+01 U235 nu-fission 9.26e-02 \n",
"\n",
" std. dev. \n",
"0 7.47e-09 \n",
@ -1436,7 +1436,7 @@
" <td>10002</td>\n",
" <td>1.000000e-08</td>\n",
" <td>1.080060e-07</td>\n",
" <td>H-1</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>4.599225</td>\n",
" <td>0.015973</td>\n",
@ -1446,7 +1446,7 @@
" <td>10002</td>\n",
" <td>1.080060e-07</td>\n",
" <td>1.166529e-06</td>\n",
" <td>H-1</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.037260</td>\n",
" <td>0.011236</td>\n",
@ -1456,7 +1456,7 @@
" <td>10002</td>\n",
" <td>1.166529e-06</td>\n",
" <td>1.259921e-05</td>\n",
" <td>H-1</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>1.662552</td>\n",
" <td>0.010280</td>\n",
@ -1466,7 +1466,7 @@
" <td>10002</td>\n",
" <td>1.259921e-05</td>\n",
" <td>1.360790e-04</td>\n",
" <td>H-1</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>1.872201</td>\n",
" <td>0.012136</td>\n",
@ -1476,7 +1476,7 @@
" <td>10002</td>\n",
" <td>1.360790e-04</td>\n",
" <td>1.469734e-03</td>\n",
" <td>H-1</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.080459</td>\n",
" <td>0.013155</td>\n",
@ -1486,7 +1486,7 @@
" <td>10002</td>\n",
" <td>1.469734e-03</td>\n",
" <td>1.587401e-02</td>\n",
" <td>H-1</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.154996</td>\n",
" <td>0.011975</td>\n",
@ -1496,7 +1496,7 @@
" <td>10002</td>\n",
" <td>1.587401e-02</td>\n",
" <td>1.714488e-01</td>\n",
" <td>H-1</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.218740</td>\n",
" <td>0.008528</td>\n",
@ -1506,7 +1506,7 @@
" <td>10002</td>\n",
" <td>1.714488e-01</td>\n",
" <td>1.851749e+00</td>\n",
" <td>H-1</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>2.010517</td>\n",
" <td>0.009187</td>\n",
@ -1516,7 +1516,7 @@
" <td>10002</td>\n",
" <td>1.851749e+00</td>\n",
" <td>2.000000e+01</td>\n",
" <td>H-1</td>\n",
" <td>H1</td>\n",
" <td>scatter</td>\n",
" <td>0.372022</td>\n",
" <td>0.003196</td>\n",
@ -1527,15 +1527,15 @@
],
"text/plain": [
" cell energy low [MeV] energy high [MeV] nuclide score mean \\\n",
"0 10002 1.00e-08 1.08e-07 H-1 scatter 4.60e+00 \n",
"1 10002 1.08e-07 1.17e-06 H-1 scatter 2.04e+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 1.87e+00 \n",
"4 10002 1.36e-04 1.47e-03 H-1 scatter 2.08e+00 \n",
"5 10002 1.47e-03 1.59e-02 H-1 scatter 2.15e+00 \n",
"6 10002 1.59e-02 1.71e-01 H-1 scatter 2.22e+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 3.72e-01 \n",
"0 10002 1.00e-08 1.08e-07 H1 scatter 4.60e+00 \n",
"1 10002 1.08e-07 1.17e-06 H1 scatter 2.04e+00 \n",
"2 10002 1.17e-06 1.26e-05 H1 scatter 1.66e+00 \n",
"3 10002 1.26e-05 1.36e-04 H1 scatter 1.87e+00 \n",
"4 10002 1.36e-04 1.47e-03 H1 scatter 2.08e+00 \n",
"5 10002 1.47e-03 1.59e-02 H1 scatter 2.15e+00 \n",
"6 10002 1.59e-02 1.71e-01 H1 scatter 2.22e+00 \n",
"7 10002 1.71e-01 1.85e+00 H1 scatter 2.01e+00 \n",
"8 10002 1.85e+00 2.00e+01 H1 scatter 3.72e-01 \n",
"\n",
" std. dev. \n",
"0 1.60e-02 \n",
@ -1557,7 +1557,7 @@
"source": [
"# \"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",
"slice_test = need_to_slice.get_slice(scores=['scatter'], nuclides=['H1'],\n",
" filters=['cell'], filter_bins=[(moderator_cell.id,)])\n",
"slice_test.get_pandas_dataframe()"
]
@ -1579,7 +1579,7 @@
"name": "python",
"nbconvert_exporter": "python",
"pygments_lexer": "ipython3",
"version": "3.5.1"
"version": "3.5.2"
}
},
"nbformat": 4,