Added docstring for Tally.swap_filter(...) routine

This commit is contained in:
Will Boyd 2015-10-03 01:04:42 -04:00
parent 9c9eb446a1
commit 0eee99ee20
9 changed files with 230 additions and 651 deletions

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" name="1.6% Fuel" surfaces="-10000" universe="10000" />
<cell id="10001" material="10002" name="1.6% Clad" surfaces="10000 -10001" universe="10000" />
<cell id="10002" material="10001" name="1.6% Moderator" surfaces="10001" universe="10000" />
<cell fill="10001" id="10003" name="root cell" surfaces="10002 -10003 10004 -10005 10006 -10007" universe="0" />
<lattice id="10001" name="1.6% Fuel - 0BA">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
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</lattice>
<surface boundary="transmission" coeffs="0.0 0.0 0.39218" id="10000" type="z-cylinder" />
<surface boundary="transmission" coeffs="0.0 0.0 0.4572" id="10001" type="z-cylinder" />
<surface boundary="reflective" coeffs="-10.71" id="10002" type="x-plane" />
<surface boundary="vacuum" coeffs="10.71" id="10003" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.71" id="10004" type="y-plane" />
<surface boundary="reflective" coeffs="10.71" id="10005" type="y-plane" />
<surface boundary="reflective" coeffs="-10.71" id="10006" type="z-plane" />
<surface boundary="reflective" coeffs="10.71" id="10007" type="z-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<default_xs>71c</default_xs>
<material id="10000" name="1.6% Fuel">
<density units="g/cm3" value="10.31341" />
<nuclide ao="0.022625" name="U-238" />
<nuclide ao="0.046007" name="O-16" />
<nuclide ao="0.00037503" name="U-235" />
</material>
<material id="10001" name="Borated Water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.024732" name="O-16" />
<nuclide ao="8.0042e-06" name="B-10" />
<nuclide ao="0.049457" name="H-1" />
</material>
<material id="10002" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.0072758" name="Zr-90" />
</material>
</materials>

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<?xml version='1.0' encoding='utf-8'?>
<plots>
<plot basis="xy" color="mat" filename="materials-xy" id="1" type="slice">
<origin>0 0 0</origin>
<width>21.5 21.5</width>
<pixels>250 250</pixels>
</plot>
</plots>

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<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>2500</particles>
<batches>20</batches>
<inactive>5</inactive>
</eigenvalue>
<source>
<space type="box">
<parameters>-10.71 -10.71 -10 10.71 10.71 10.0</parameters>
</space>
</source>
<output>
<tallies>false</tallies>
<summary>true</summary>
</output>
<trigger>
<active>true</active>
<max_batches>200</max_batches>
</trigger>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<width>1.26 1.26</width>
</mesh>
<tally id="10000" name="mesh tally">
<filter bins="1" type="mesh" />
<filter bins="0.0 6.25e-07 20.0" type="energy" />
<scores>fission nu-fission</scores>
</tally>
<tally id="10001" name="cell tally">
<filter bins="10000" type="cell" />
<nuclides>U-235 U-238</nuclides>
<scores>scatter-y2</scores>
</tally>
<tally id="10002" name="distribcell tally">
<filter bins="10002" type="distribcell" />
<scores>absorption scatter</scores>
<trigger scores="absorption" threshold="5e-05" type="std_dev" />
</tally>
</tallies>

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@ -369,7 +369,7 @@
"outputs": [
{
"data": {
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"image/png": "iVBORw0KGgoAAAANSUhEUgAAAPoAAAD6AgMAAAD1grKuAAAABGdBTUEAALGPC/xhBQAAAAFzUkdC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\nVDAxOjAzOjI5LTA0OjAwtCXLZQAAAABJRU5ErkJggg==\n",
"text/plain": [
"<IPython.core.display.Image object>"
]
@ -580,7 +580,7 @@
" License: http://mit-crpg.github.io/openmc/license.html\n",
" Version: 0.7.0\n",
" Git SHA1: e0c2aace2e73367536fa03e153b67a2d038cd2b3\n",
" Date/Time: 2015-10-03 00:24:54\n",
" Date/Time: 2015-10-03 01:03:29\n",
" MPI Processes: 1\n",
"\n",
" ===========================================================================\n",
@ -636,20 +636,20 @@
"\n",
" =======================> TIMING STATISTICS <=======================\n",
"\n",
" Total time for initialization = 7.0100E-01 seconds\n",
" Reading cross sections = 1.5800E-01 seconds\n",
" Total time in simulation = 2.0485E+01 seconds\n",
" Time in transport only = 2.0465E+01 seconds\n",
" Time in inactive batches = 3.0920E+00 seconds\n",
" Time in active batches = 1.7393E+01 seconds\n",
" Time synchronizing fission bank = 5.0000E-03 seconds\n",
" Sampling source sites = 4.0000E-03 seconds\n",
" Total time for initialization = 4.1300E-01 seconds\n",
" Reading cross sections = 9.0000E-02 seconds\n",
" Total time in simulation = 2.1398E+01 seconds\n",
" Time in transport only = 2.1378E+01 seconds\n",
" Time in inactive batches = 2.0260E+00 seconds\n",
" Time in active batches = 1.9372E+01 seconds\n",
" Time synchronizing fission bank = 2.0000E-03 seconds\n",
" Sampling source sites = 0.0000E+00 seconds\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 = 2.1200E+01 seconds\n",
" Calculation Rate (inactive) = 4042.69 neutrons/second\n",
" Calculation Rate (active) = 2156.04 neutrons/second\n",
" Time accumulating tallies = 1.0000E-03 seconds\n",
" Total time for finalization = 3.0000E-03 seconds\n",
" Total time elapsed = 2.1823E+01 seconds\n",
" Calculation Rate (inactive) = 6169.79 neutrons/second\n",
" Calculation Rate (active) = 1935.78 neutrons/second\n",
"\n",
" ============================> RESULTS <============================\n",
"\n",
@ -721,7 +721,20 @@
"collapsed": false,
"scrolled": true
},
"outputs": [],
"outputs": [
{
"ename": "KeyError",
"evalue": "10003",
"output_type": "error",
"traceback": [
"\u001b[1;31m---------------------------------------------------------------------------\u001b[0m",
"\u001b[1;31mKeyError\u001b[0m Traceback (most recent call last)",
"\u001b[1;32m<ipython-input-25-3cd87b8121ef>\u001b[0m in \u001b[0;36m<module>\u001b[1;34m()\u001b[0m\n\u001b[0;32m 1\u001b[0m \u001b[1;31m# Load the summary file and link with statepoint\u001b[0m\u001b[1;33m\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 2\u001b[0m \u001b[0msu\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0mSummary\u001b[0m\u001b[1;33m(\u001b[0m\u001b[1;34m'summary.h5'\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m----> 3\u001b[1;33m \u001b[0msp\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mlink_with_summary\u001b[0m\u001b[1;33m(\u001b[0m\u001b[0msu\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m",
"\u001b[1;32m/usr/local/lib/python2.7/dist-packages/openmc-0.7.0-py2.7.egg/openmc/statepoint.pyc\u001b[0m in \u001b[0;36mlink_with_summary\u001b[1;34m(self, summary)\u001b[0m\n\u001b[0;32m 610\u001b[0m \u001b[1;32mfor\u001b[0m \u001b[0mtally_id\u001b[0m\u001b[1;33m,\u001b[0m \u001b[0mtally\u001b[0m \u001b[1;32min\u001b[0m \u001b[0mself\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mtallies\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mitems\u001b[0m\u001b[1;33m(\u001b[0m\u001b[1;33m)\u001b[0m\u001b[1;33m:\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 611\u001b[0m \u001b[1;31m# Get the Tally name from the summary file\u001b[0m\u001b[1;33m\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[1;32m--> 612\u001b[1;33m \u001b[0mtally\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mname\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0msummary\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mtallies\u001b[0m\u001b[1;33m[\u001b[0m\u001b[0mtally_id\u001b[0m\u001b[1;33m]\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mname\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0m\u001b[0;32m 613\u001b[0m \u001b[0mtally\u001b[0m\u001b[1;33m.\u001b[0m\u001b[0mwith_summary\u001b[0m \u001b[1;33m=\u001b[0m \u001b[0mTrue\u001b[0m\u001b[1;33m\u001b[0m\u001b[0m\n\u001b[0;32m 614\u001b[0m \u001b[1;33m\u001b[0m\u001b[0m\n",
"\u001b[1;31mKeyError\u001b[0m: 10003"
]
}
],
"source": [
"# Load the summary file and link with statepoint\n",
"su = Summary('summary.h5')\n",
@ -739,47 +752,11 @@
},
{
"cell_type": "code",
"execution_count": 26,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
" <th>std. dev.</th>\n",
" </tr>\n",
" </thead>\n",
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>total</td>\n",
" <td>(nu-fission / absorption)</td>\n",
" <td>1.046353</td>\n",
" <td>0.00935</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" nuclide score mean std. dev.\n",
"0 total (nu-fission / absorption) 1.046353 0.00935"
]
},
"execution_count": 26,
"metadata": {},
"output_type": "execute_result"
}
],
"outputs": [],
"source": [
"# Compute k-infinity using tally arithmetic\n",
"fiss_rate = sp.get_tally(name='fiss. rate')\n",
@ -799,49 +776,11 @@
},
{
"cell_type": "code",
"execution_count": 27,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>energy [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
" <th>std. dev.</th>\n",
" </tr>\n",
" </thead>\n",
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>(0.0e+00 - 6.2e-01)</td>\n",
" <td>total</td>\n",
" <td>absorption</td>\n",
" <td>0.95873</td>\n",
" <td>0.00774</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" energy [MeV] nuclide score mean std. dev.\n",
"0 (0.0e+00 - 6.2e-01) total absorption 0.95873 0.00774"
]
},
"execution_count": 27,
"metadata": {},
"output_type": "execute_result"
}
],
"outputs": [],
"source": [
"# Compute resonance escape probability using tally arithmetic\n",
"therm_abs_rate = sp.get_tally(name='therm. abs. rate')\n",
@ -859,47 +798,11 @@
},
{
"cell_type": "code",
"execution_count": 28,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
" <th>std. dev.</th>\n",
" </tr>\n",
" </thead>\n",
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>total</td>\n",
" <td>nu-fission</td>\n",
" <td>1.091622</td>\n",
" <td>0.011163</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" nuclide score mean std. dev.\n",
"0 total nu-fission 1.091622 0.011163"
]
},
"execution_count": 28,
"metadata": {},
"output_type": "execute_result"
}
],
"outputs": [],
"source": [
"# Compute fast fission factor factor using tally arithmetic\n",
"therm_fiss_rate = sp.get_tally(name='therm. fiss. rate')\n",
@ -918,51 +821,11 @@
},
{
"cell_type": "code",
"execution_count": 29,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>energy [MeV]</th>\n",
" <th>cell</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
" <th>std. dev.</th>\n",
" </tr>\n",
" </thead>\n",
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>(0.0e+00 - 6.2e-01)</td>\n",
" <td>10000</td>\n",
" <td>total</td>\n",
" <td>absorption</td>\n",
" <td>0.802012</td>\n",
" <td>0.006609</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" energy [MeV] cell nuclide score mean std. dev.\n",
"0 (0.0e+00 - 6.2e-01) 10000 total absorption 0.802012 0.006609"
]
},
"execution_count": 29,
"metadata": {},
"output_type": "execute_result"
}
],
"outputs": [],
"source": [
"# Compute thermal flux utilization factor using tally arithmetic\n",
"fuel_therm_abs_rate = sp.get_tally(name='fuel therm. abs. rate')\n",
@ -979,49 +842,11 @@
},
{
"cell_type": "code",
"execution_count": 30,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>energy [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
" <th>std. dev.</th>\n",
" </tr>\n",
" </thead>\n",
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>(0.0e+00 - 6.2e-01)</td>\n",
" <td>total</td>\n",
" <td>(nu-fission / absorption)</td>\n",
" <td>1.246604</td>\n",
" <td>0.011825</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" energy [MeV] nuclide score mean std. dev.\n",
"0 (0.0e+00 - 6.2e-01) total (nu-fission / absorption) 1.246604 0.011825"
]
},
"execution_count": 30,
"metadata": {},
"output_type": "execute_result"
}
],
"outputs": [],
"source": [
"# Compute neutrons produced per absorption (eta) using tally arithmetic\n",
"eta = therm_fiss_rate / fuel_therm_abs_rate\n",
@ -1037,52 +862,11 @@
},
{
"cell_type": "code",
"execution_count": 31,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>energy [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
" <th>std. dev.</th>\n",
" </tr>\n",
" </thead>\n",
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>(0.0e+00 - 6.2e-01)</td>\n",
" <td>total</td>\n",
" <td>(((absorption * nu-fission) * absorption) * (n...</td>\n",
" <td>1.046353</td>\n",
" <td>0.01894</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" energy [MeV] nuclide \\\n",
"0 (0.0e+00 - 6.2e-01) total \n",
"\n",
" score mean std. dev. \n",
"0 (((absorption * nu-fission) * absorption) * (n... 1.046353 0.01894 "
]
},
"execution_count": 31,
"metadata": {},
"output_type": "execute_result"
}
],
"outputs": [],
"source": [
"keff = res_esc * fast_fiss * therm_util * eta\n",
"keff.get_pandas_dataframe()"
@ -1099,7 +883,7 @@
},
{
"cell_type": "code",
"execution_count": 32,
"execution_count": null,
"metadata": {
"collapsed": false,
"scrolled": true
@ -1115,131 +899,11 @@
},
{
"cell_type": "code",
"execution_count": 33,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
" <th>std. dev.</th>\n",
" </tr>\n",
" </thead>\n",
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>6.641746e-07</td>\n",
" <td>6.859257e-09</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>2.099861e-01</td>\n",
" <td>1.966887e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>3.556665e-01</td>\n",
" <td>3.717881e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>5.554650e-03</td>\n",
" <td>5.218094e-05</td>\n",
" </tr>\n",
" <tr>\n",
" <th>4</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>7.165057e-03</td>\n",
" <td>5.625590e-05</td>\n",
" </tr>\n",
" <tr>\n",
" <th>5</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>(U-238 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>2.276535e-01</td>\n",
" <td>8.544314e-04</td>\n",
" </tr>\n",
" <tr>\n",
" <th>6</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(nu-fission / flux)</td>\n",
" <td>8.089493e-03</td>\n",
" <td>5.080374e-05</td>\n",
" </tr>\n",
" <tr>\n",
" <th>7</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>(U-235 / total)</td>\n",
" <td>(scatter / flux)</td>\n",
" <td>3.370111e-03</td>\n",
" <td>1.361116e-05</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide score \\\n",
"0 10000 (0.0e+00 - 6.3e-07) (U-238 / total) (nu-fission / flux) \n",
"1 10000 (0.0e+00 - 6.3e-07) (U-238 / total) (scatter / flux) \n",
"2 10000 (0.0e+00 - 6.3e-07) (U-235 / total) (nu-fission / flux) \n",
"3 10000 (0.0e+00 - 6.3e-07) (U-235 / total) (scatter / flux) \n",
"4 10000 (6.3e-07 - 2.0e+01) (U-238 / total) (nu-fission / flux) \n",
"5 10000 (6.3e-07 - 2.0e+01) (U-238 / total) (scatter / flux) \n",
"6 10000 (6.3e-07 - 2.0e+01) (U-235 / total) (nu-fission / flux) \n",
"7 10000 (6.3e-07 - 2.0e+01) (U-235 / total) (scatter / flux) \n",
"\n",
" mean std. dev. \n",
"0 6.641746e-07 6.859257e-09 \n",
"1 2.099861e-01 1.966887e-03 \n",
"2 3.556665e-01 3.717881e-03 \n",
"3 5.554650e-03 5.218094e-05 \n",
"4 7.165057e-03 5.625590e-05 \n",
"5 2.276535e-01 8.544314e-04 \n",
"6 8.089493e-03 5.080374e-05 \n",
"7 3.370111e-03 1.361116e-05 "
]
},
"execution_count": 33,
"metadata": {},
"output_type": "execute_result"
}
],
"outputs": [],
"source": [
"fuel_xs = fuel_rxn_rates / flux\n",
"fuel_xs.get_pandas_dataframe()"
@ -1254,23 +918,11 @@
},
{
"cell_type": "code",
"execution_count": 34,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"name": "stdout",
"output_type": "stream",
"text": [
"[[[ 6.64174599e-07]\n",
" [ 3.55666541e-01]]\n",
"\n",
" [[ 7.16505734e-03]\n",
" [ 8.08949336e-03]]]\n"
]
}
],
"outputs": [],
"source": [
"# Show how to use Tally.get_values(...) with a CrossScore\n",
"nu_fiss_xs = fuel_xs.get_values(scores=['(nu-fission / flux)'])\n",
@ -1286,21 +938,11 @@
},
{
"cell_type": "code",
"execution_count": 35,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"name": "stdout",
"output_type": "stream",
"text": [
"[[[ 0.00555465]]\n",
"\n",
" [[ 0.00337011]]]\n"
]
}
],
"outputs": [],
"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",
@ -1310,20 +952,11 @@
},
{
"cell_type": "code",
"execution_count": 36,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"name": "stdout",
"output_type": "stream",
"text": [
"[[[ 0.22765348]\n",
" [ 0.00337011]]]\n"
]
}
],
"outputs": [],
"source": [
"# Show how to use Tally.get_values(...) with a CrossFilter and CrossScore\n",
"fast_scatter_xs = fuel_xs.get_values(filters=['energy'], \n",
@ -1341,81 +974,11 @@
},
{
"cell_type": "code",
"execution_count": 37,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
" <th>std. dev.</th>\n",
" </tr>\n",
" </thead>\n",
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>U-238</td>\n",
" <td>nu-fission</td>\n",
" <td>0.000002</td>\n",
" <td>1.284890e-08</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>10000</td>\n",
" <td>(0.0e+00 - 6.3e-07)</td>\n",
" <td>U-235</td>\n",
" <td>nu-fission</td>\n",
" <td>0.867982</td>\n",
" <td>7.022256e-03</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>U-238</td>\n",
" <td>nu-fission</td>\n",
" <td>0.082801</td>\n",
" <td>6.087096e-04</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
" <td>10000</td>\n",
" <td>(6.3e-07 - 2.0e+01)</td>\n",
" <td>U-235</td>\n",
" <td>nu-fission</td>\n",
" <td>0.093484</td>\n",
" <td>5.275039e-04</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide score mean std. dev.\n",
"0 10000 (0.0e+00 - 6.3e-07) U-238 nu-fission 0.000002 1.284890e-08\n",
"1 10000 (0.0e+00 - 6.3e-07) U-235 nu-fission 0.867982 7.022256e-03\n",
"2 10000 (6.3e-07 - 2.0e+01) U-238 nu-fission 0.082801 6.087096e-04\n",
"3 10000 (6.3e-07 - 2.0e+01) U-235 nu-fission 0.093484 5.275039e-04"
]
},
"execution_count": 37,
"metadata": {},
"output_type": "execute_result"
}
],
"outputs": [],
"source": [
"# \"Slice\" the nu-fission data into a new derived Tally\n",
"nu_fission_rates = fuel_rxn_rates.get_slice(scores=['nu-fission'])\n",
@ -1424,131 +987,11 @@
},
{
"cell_type": "code",
"execution_count": 38,
"execution_count": null,
"metadata": {
"collapsed": false
},
"outputs": [
{
"data": {
"text/html": [
"<div style=\"max-height:1000px;max-width:1500px;overflow:auto;\">\n",
"<table border=\"1\" class=\"dataframe\">\n",
" <thead>\n",
" <tr style=\"text-align: right;\">\n",
" <th></th>\n",
" <th>cell</th>\n",
" <th>energy [MeV]</th>\n",
" <th>nuclide</th>\n",
" <th>score</th>\n",
" <th>mean</th>\n",
" <th>std. dev.</th>\n",
" </tr>\n",
" </thead>\n",
" <tbody>\n",
" <tr>\n",
" <th>0</th>\n",
" <td>10002</td>\n",
" <td>(1.0e-08 - 1.1e-07)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>4.620525</td>\n",
" <td>0.038249</td>\n",
" </tr>\n",
" <tr>\n",
" <th>1</th>\n",
" <td>10002</td>\n",
" <td>(1.1e-07 - 1.2e-06)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.036841</td>\n",
" <td>0.013203</td>\n",
" </tr>\n",
" <tr>\n",
" <th>2</th>\n",
" <td>10002</td>\n",
" <td>(1.2e-06 - 1.3e-05)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>1.659916</td>\n",
" <td>0.010107</td>\n",
" </tr>\n",
" <tr>\n",
" <th>3</th>\n",
" <td>10002</td>\n",
" <td>(1.3e-05 - 1.4e-04)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>1.861546</td>\n",
" <td>0.013328</td>\n",
" </tr>\n",
" <tr>\n",
" <th>4</th>\n",
" <td>10002</td>\n",
" <td>(1.4e-04 - 1.5e-03)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.049664</td>\n",
" <td>0.008215</td>\n",
" </tr>\n",
" <tr>\n",
" <th>5</th>\n",
" <td>10002</td>\n",
" <td>(1.5e-03 - 1.6e-02)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.162157</td>\n",
" <td>0.010245</td>\n",
" </tr>\n",
" <tr>\n",
" <th>6</th>\n",
" <td>10002</td>\n",
" <td>(1.6e-02 - 1.7e-01)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>2.224496</td>\n",
" <td>0.013796</td>\n",
" </tr>\n",
" <tr>\n",
" <th>7</th>\n",
" <td>10002</td>\n",
" <td>(1.7e-01 - 1.9e+00)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>1.997585</td>\n",
" <td>0.009161</td>\n",
" </tr>\n",
" <tr>\n",
" <th>8</th>\n",
" <td>10002</td>\n",
" <td>(1.9e+00 - 2.0e+01)</td>\n",
" <td>H-1</td>\n",
" <td>scatter</td>\n",
" <td>0.373472</td>\n",
" <td>0.003922</td>\n",
" </tr>\n",
" </tbody>\n",
"</table>\n",
"</div>"
],
"text/plain": [
" cell energy [MeV] nuclide score mean std. dev.\n",
"0 10002 (1.0e-08 - 1.1e-07) H-1 scatter 4.620525 0.038249\n",
"1 10002 (1.1e-07 - 1.2e-06) H-1 scatter 2.036841 0.013203\n",
"2 10002 (1.2e-06 - 1.3e-05) H-1 scatter 1.659916 0.010107\n",
"3 10002 (1.3e-05 - 1.4e-04) H-1 scatter 1.861546 0.013328\n",
"4 10002 (1.4e-04 - 1.5e-03) H-1 scatter 2.049664 0.008215\n",
"5 10002 (1.5e-03 - 1.6e-02) H-1 scatter 2.162157 0.010245\n",
"6 10002 (1.6e-02 - 1.7e-01) H-1 scatter 2.224496 0.013796\n",
"7 10002 (1.7e-01 - 1.9e+00) H-1 scatter 1.997585 0.009161\n",
"8 10002 (1.9e+00 - 2.0e+01) H-1 scatter 0.373472 0.003922"
]
},
"execution_count": 38,
"metadata": {},
"output_type": "execute_result"
}
],
"outputs": [],
"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",