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removed updates to mgxs notebooks
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parent
c35eac2c06
commit
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2 changed files with 161 additions and 153 deletions
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@ -91,7 +91,7 @@
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"\n",
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"$$\\sigma_{n,x,k,g} = \\frac{\\int_{E_{g}}^{E_{g-1}}\\mathrm{d}E'\\int_{\\mathbf{r} \\in V_{k}}\\mathrm{d}\\mathbf{r}\\sigma_{n,x}(\\mathbf{r},E')\\Phi(\\mathbf{r},E')}{\\int_{E_{g}}^{E_{g-1}}\\mathrm{d}E'\\int_{\\mathbf{r} \\in V_{k}}\\mathrm{d}\\mathbf{r}\\Phi(\\mathbf{r},E')}$$\n",
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"\n",
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"This scalar flux-weighted average microscopic cross section is computed by `openmc.mgxs` for most multi-group cross sections, including total, absorption, and fission reaction types. These double integrals are stochastically computed with OpenMC's tally system - in particular, [filters](https://mit-crpg.github.io/openmc/pythonapi/filter.html) on the energy range and spatial zone (material, cell, universe, or mesh) define the bounds of integration for both numerator and denominator."
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"This scalar flux-weighted average microscopic cross section is computed by `openmc.mgxs` for most multi-group cross sections, including total, absorption, and fission reaction types. These double integrals are stochastically computed with OpenMC's tally system - in particular, [filters](https://mit-crpg.github.io/openmc/pythonapi/filter.html) on the energy range and spatial zone (material, cell or universe) define the bounds of integration for both numerator and denominator."
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]
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},
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{
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@ -513,10 +513,9 @@
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"\n",
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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: 16e74656b028875a7ebcb90df07293c5f1cc56a4\n",
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" Date/Time: 2016-07-29 13:40:25\n",
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" MPI Processes: 1\n",
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" Version: 0.7.1\n",
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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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"\n",
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" ===========================================================================\n",
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" ========================> INITIALIZATION <=========================\n",
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@ -526,11 +525,11 @@
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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 H1.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/H1_71c.h5\n",
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" Reading O16.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/O16_71c.h5\n",
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" Reading U235.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/U235_71c.h5\n",
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" Reading U238.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/U238_71c.h5\n",
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" Reading Zr90.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/Zr90_71c.h5\n",
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" Reading H1.71c from /home/romano/openmc/data/nndc_hdf5/H1_71c.h5\n",
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" Reading O16.71c from /home/romano/openmc/data/nndc_hdf5/O16_71c.h5\n",
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" Reading U235.71c from /home/romano/openmc/data/nndc_hdf5/U235_71c.h5\n",
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" Reading U238.71c from /home/romano/openmc/data/nndc_hdf5/U238_71c.h5\n",
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" Reading Zr90.71c from /home/romano/openmc/data/nndc_hdf5/Zr90_71c.h5\n",
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" Maximum neutron transport energy: 20.0000 MeV for H1.71c\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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@ -601,20 +600,20 @@
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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 = 3.9900E-01 seconds\n",
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" Reading cross sections = 2.1800E-01 seconds\n",
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" Total time in simulation = 2.0870E+01 seconds\n",
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" Time in transport only = 2.0855E+01 seconds\n",
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" Time in inactive batches = 2.3100E+00 seconds\n",
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" Time in active batches = 1.8560E+01 seconds\n",
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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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" Time in transport only = 1.9869E+01 seconds\n",
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" Time in inactive batches = 2.6590E+00 seconds\n",
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" Time in active batches = 1.7223E+01 seconds\n",
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" Time synchronizing fission bank = 4.0000E-03 seconds\n",
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" Sampling source sites = 3.0000E-03 seconds\n",
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" SEND/RECV source sites = 1.0000E-03 seconds\n",
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" Time accumulating tallies = 2.0000E-03 seconds\n",
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" Total time for finalization = 1.0000E-03 seconds\n",
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" Total time elapsed = 2.1283E+01 seconds\n",
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" Calculation Rate (inactive) = 10822.5 neutrons/second\n",
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" Calculation Rate (active) = 5387.93 neutrons/second\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 = 0.0000E+00 seconds\n",
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" Total time for finalization = 0.0000E+00 seconds\n",
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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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"\n",
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" ============================> RESULTS <============================\n",
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"\n",
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@ -815,12 +814,30 @@
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"cell_type": "markdown",
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"metadata": {},
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"source": [
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"The following code snippet shows how to export all three `MGXS` to the same HDF5 binary data store."
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"Each multi-group cross section object can be easily exported to a variety of file formats, including CSV, Excel, and LaTeX for storage or data processing."
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]
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},
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{
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"cell_type": "code",
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"execution_count": 20,
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"metadata": {
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"collapsed": true
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},
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"outputs": [],
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"source": [
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"absorption.export_xs_data(filename='absorption-xs', format='excel')"
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]
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},
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{
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"cell_type": "markdown",
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"metadata": {},
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"source": [
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"The following code snippet shows how to export all three `MGXS` to the same HDF5 binary data store."
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]
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},
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{
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"cell_type": "code",
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"execution_count": 21,
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"metadata": {
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"collapsed": false
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},
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@ -847,7 +864,7 @@
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},
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{
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"cell_type": "code",
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"execution_count": 21,
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"execution_count": 22,
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"metadata": {
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"collapsed": false
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},
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@ -877,7 +894,7 @@
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" <td>6.250000e-07</td>\n",
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" <td>total</td>\n",
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" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
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" <td>-3.996803e-15</td>\n",
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" <td>-3.774758e-15</td>\n",
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" <td>0.011292</td>\n",
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" </tr>\n",
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" <tr>\n",
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@ -887,7 +904,7 @@
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" <td>2.000000e+01</td>\n",
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" <td>total</td>\n",
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" <td>(((total / flux) - (absorption / flux)) - (sca...</td>\n",
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" <td>5.551115e-16</td>\n",
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" <td>1.443290e-15</td>\n",
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" <td>0.002570</td>\n",
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" </tr>\n",
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" </tbody>\n",
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@ -900,11 +917,11 @@
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"1 1 6.25e-07 2.00e+01 total \n",
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"\n",
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" score mean std. dev. \n",
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"0 (((total / flux) - (absorption / flux)) - (sca... -4.00e-15 1.13e-02 \n",
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"1 (((total / flux) - (absorption / flux)) - (sca... 5.55e-16 2.57e-03 "
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"0 (((total / flux) - (absorption / flux)) - (sca... -3.77e-15 1.13e-02 \n",
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"1 (((total / flux) - (absorption / flux)) - (sca... 1.44e-15 2.57e-03 "
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]
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},
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"execution_count": 21,
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"execution_count": 22,
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"metadata": {},
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"output_type": "execute_result"
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}
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@ -926,7 +943,7 @@
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},
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{
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"cell_type": "code",
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"execution_count": 22,
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"execution_count": 23,
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"metadata": {
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"collapsed": false
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},
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@ -983,7 +1000,7 @@
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"1 ((absorption / flux) / (total / flux)) 1.93e-02 9.46e-05 "
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]
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},
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"execution_count": 22,
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"execution_count": 23,
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"metadata": {},
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"output_type": "execute_result"
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}
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@ -998,7 +1015,7 @@
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},
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{
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"cell_type": "code",
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"execution_count": 23,
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"execution_count": 24,
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"metadata": {
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"collapsed": false
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},
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@ -1055,7 +1072,7 @@
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"1 ((scatter / flux) / (total / flux)) 9.81e-01 3.74e-03 "
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]
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},
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"execution_count": 23,
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"execution_count": 24,
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"metadata": {},
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"output_type": "execute_result"
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}
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@ -1077,7 +1094,7 @@
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},
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{
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"cell_type": "code",
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"execution_count": 24,
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"execution_count": 25,
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"metadata": {
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"collapsed": false
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},
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@ -1107,7 +1124,7 @@
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" <td>6.250000e-07</td>\n",
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" <td>total</td>\n",
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" <td>(((absorption / flux) / (total / flux)) + ((sc...</td>\n",
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" <td>1</td>\n",
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" <td>1.0</td>\n",
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" <td>0.007763</td>\n",
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" </tr>\n",
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" <tr>\n",
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" <td>2.000000e+01</td>\n",
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" <td>total</td>\n",
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" <td>(((absorption / flux) / (total / flux)) + ((sc...</td>\n",
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" <td>1</td>\n",
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" <td>1.0</td>\n",
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" <td>0.003739</td>\n",
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" </tr>\n",
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" </tbody>\n",
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"1 (((absorption / flux) / (total / flux)) + ((sc... 1.00e+00 3.74e-03 "
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]
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},
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"execution_count": 24,
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"execution_count": 25,
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"metadata": {},
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"output_type": "execute_result"
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}
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"# The scattering-to-total ratio is a derived tally which can generate Pandas DataFrames for inspection\n",
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"sum_ratio.get_pandas_dataframe()"
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]
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},
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{
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"cell_type": "code",
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"execution_count": null,
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"metadata": {
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"collapsed": true
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},
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"outputs": [],
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"source": []
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}
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],
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"metadata": {
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