adding export_to_xml to run and updating tests

This commit is contained in:
Ethan Peterson 2023-02-28 11:31:04 -05:00
parent 7200d42644
commit 11e618fe81
111 changed files with 13560 additions and 13643 deletions

View file

@ -596,7 +596,8 @@ class Model:
def run(self, particles=None, threads=None, geometry_debug=False,
restart_file=None, tracks=False, output=True, cwd='.',
openmc_exec='openmc', mpi_args=None, event_based=None):
openmc_exec='openmc', mpi_args=None, event_based=None,
export_model_xml=True):
"""Runs OpenMC. If the C API has been initialized, then the C API is
used, otherwise, this method creates the XML files and runs OpenMC via
a system call. In both cases this method returns the path to the last
@ -639,6 +640,9 @@ class Model:
event_based : None or bool, optional
Turns on event-based parallelism if True. If None, the value in
the Settings will be used.
export_model_xml : bool, optional
Exports a single model.xml file rather than separate files.
Defaults to True.
Returns
-------
@ -688,7 +692,10 @@ class Model:
else:
# Then run via the command line
self.export_to_xml()
if export_model_xml:
self.export_to_model_xml()
else:
self.export_to_xml()
openmc.run(particles, threads, geometry_debug, restart_file,
tracks, output, Path('.'), openmc_exec, mpi_args,
event_based)

View file

@ -291,7 +291,7 @@ CSGCell::CSGCell(pugi::xml_node cell_node)
if (fill_present) {
fill_ = std::stoi(get_node_value(cell_node, "fill"));
if (fill_ == universe_) {
fatal_error(fmt::format("Cell {} is filled with the same universe that"
fatal_error(fmt::format("Cell {} is filled with the same universe that "
"it is contained in.",
id_));
}

View file

@ -1,38 +1,38 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="2" region="1" universe="1" />
<cell fill="1" id="3" region="2 -3 4 -5 6 -8" rotation="10 20 30" universe="2" />
<cell fill="1" id="4" region="2 -3 4 -5 8 -7" translation="0 0 15" universe="2" />
<surface coeffs="1.0 0.0 0.0 5.0" id="1" type="sphere" />
<surface boundary="vacuum" coeffs="-7.5" id="2" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="7.5" id="3" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-7.5" id="4" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="7.5" id="5" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-7.5" id="6" type="z-plane" />
<surface boundary="vacuum" coeffs="22.5" id="7" type="z-plane" />
<surface coeffs="7.5" id="8" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="10.0" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2">
<density units="g/cc" value="0.1" />
<nuclide ao="0.1" name="H1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>10000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4.0 -4.0 -4.0 4.0 4.0 4.0</parameters>
</space>
</source>
</settings>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="10.0" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2">
<density units="g/cc" value="0.1" />
<nuclide ao="0.1" name="H1" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="2" region="1" universe="1" />
<cell fill="1" id="3" region="2 -3 4 -5 6 -8" rotation="10 20 30" universe="2" />
<cell fill="1" id="4" region="2 -3 4 -5 8 -7" translation="0 0 15" universe="2" />
<surface coeffs="1.0 0.0 0.0 5.0" id="1" type="sphere" />
<surface boundary="vacuum" coeffs="-7.5" id="2" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="7.5" id="3" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-7.5" id="4" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="7.5" id="5" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-7.5" id="6" type="z-plane" />
<surface boundary="vacuum" coeffs="22.5" id="7" type="z-plane" />
<surface coeffs="7.5" id="8" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>10000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4.0 -4.0 -4.0 4.0 4.0 4.0</parameters>
</space>
</source>
</settings>
</model>

View file

@ -1,19 +1,168 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="202" id="1" region="9 -10 11 -12 13 -14" universe="0" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
<model>
<materials>
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector / Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell fill="202" id="1" region="9 -10 11 -12 13 -14" universe="0" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
@ -31,197 +180,47 @@
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="202" name="3x3 Core Lattice">
<pitch>21.42 21.42</pitch>
<dimension>3 3</dimension>
<lower_left>-32.13 -32.13</lower_left>
<universes>
</lattice>
<lattice id="202" name="3x3 Core Lattice">
<pitch>21.42 21.42</pitch>
<dimension>3 3</dimension>
<lower_left>-32.13 -32.13</lower_left>
<universes>
8 7 7
8 8 8
7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface boundary="reflective" coeffs="-32.13" id="9" type="x-plane" />
<surface boundary="reflective" coeffs="32.13" id="10" type="x-plane" />
<surface boundary="reflective" coeffs="-32.13" id="11" type="y-plane" />
<surface boundary="reflective" coeffs="32.13" id="12" type="y-plane" />
<surface boundary="reflective" coeffs="0" id="13" type="z-plane" />
<surface boundary="reflective" coeffs="32.13" id="14" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector / Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-32 -32 0 32 32 32</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="distribcell">
<bins>27</bins>
</filter>
<tally id="27" name="distribcell tally">
<filters>1</filters>
<scores>nu-fission</scores>
</tally>
</tallies>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface boundary="reflective" coeffs="-32.13" id="9" type="x-plane" />
<surface boundary="reflective" coeffs="32.13" id="10" type="x-plane" />
<surface boundary="reflective" coeffs="-32.13" id="11" type="y-plane" />
<surface boundary="reflective" coeffs="32.13" id="12" type="y-plane" />
<surface boundary="reflective" coeffs="0" id="13" type="z-plane" />
<surface boundary="reflective" coeffs="32.13" id="14" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-32 -32 0 32 32 32</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="distribcell">
<bins>27</bins>
</filter>
<tally id="27" name="distribcell tally">
<filters>1</filters>
<scores>nu-fission</scores>
</tally>
</tallies>
</model>

View file

@ -1,45 +1,45 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="2" region="1 -2" universe="1" />
<cell id="3" material="3" region="2" universe="1" />
<cell fill="1" id="4" universe="2" />
<cell fill="3" id="5" region="3 -4 5 -6" universe="4" />
<lattice id="3">
<pitch>4.0 4.0</pitch>
<dimension>2 2</dimension>
<lower_left>-4.0 -4.0</lower_left>
<universes>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="11" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="cladding">
<density units="g/cc" value="6.44" />
<nuclide ao="1.0" name="Zr90" />
</material>
<material id="3" name="water">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="2" region="1 -2" universe="1" />
<cell id="3" material="3" region="2" universe="1" />
<cell fill="1" id="4" universe="2" />
<cell fill="3" id="5" region="3 -4 5 -6" universe="4" />
<lattice id="3">
<pitch>4.0 4.0</pitch>
<dimension>2 2</dimension>
<lower_left>-4.0 -4.0</lower_left>
<universes>
2 2
2 2 </universes>
</lattice>
<surface coeffs="0.0 0.0 1.5" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 1.7" id="2" type="z-cylinder" />
<surface boundary="reflective" coeffs="-4.0" id="3" name="minimum x" type="x-plane" />
<surface boundary="reflective" coeffs="4.0" id="4" name="maximum x" type="x-plane" />
<surface boundary="reflective" coeffs="-4.0" id="5" name="minimum y" type="y-plane" />
<surface boundary="reflective" coeffs="4.0" id="6" name="maximum y" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="11" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="cladding">
<density units="g/cc" value="6.44" />
<nuclide ao="1.0" name="Zr90" />
</material>
<material id="3" name="water">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>1</inactive>
</settings>
</lattice>
<surface coeffs="0.0 0.0 1.5" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 1.7" id="2" type="z-cylinder" />
<surface boundary="reflective" coeffs="-4.0" id="3" name="minimum x" type="x-plane" />
<surface boundary="reflective" coeffs="4.0" id="4" name="maximum x" type="x-plane" />
<surface boundary="reflective" coeffs="-4.0" id="5" name="minimum y" type="y-plane" />
<surface boundary="reflective" coeffs="4.0" id="6" name="maximum y" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>1</inactive>
</settings>
</model>

View file

@ -1,37 +1,36 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0" />
<surface boundary="reflective" coeffs="-1" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="1" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<create_fission_neutrons>false</create_fission_neutrons>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="1">
<scores>flux</scores>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0" />
<surface boundary="reflective" coeffs="-1" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="1" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<create_fission_neutrons>false</create_fission_neutrons>
</settings>
<tallies>
<tally id="1">
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -4,14 +4,14 @@ from tests.testing_harness import PyAPITestHarness
class CreateFissionNeutronsTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
# Material is composed of H-1 and U-235
mat = openmc.Material(material_id=1, name='mat')
mat.set_density('atom/b-cm', 0.069335)
mat.add_nuclide('H1', 40.0)
mat.add_nuclide('U235', 1.0)
materials_file = openmc.Materials([mat])
materials_file.export_to_xml()
self._model.materials = openmc.Materials([mat])
# Cell is box with reflective boundary
x1 = openmc.XPlane(surface_id=1, x0=-1)
@ -27,8 +27,7 @@ class CreateFissionNeutronsTestHarness(PyAPITestHarness):
box.fill = mat
root = openmc.Universe(universe_id=0, name='root universe')
root.add_cell(box)
geometry = openmc.Geometry(root)
geometry.export_to_xml()
self._model.geometry = openmc.Geometry(root)
# Set the running parameters
settings_file = openmc.Settings()
@ -41,14 +40,14 @@ class CreateFissionNeutronsTestHarness(PyAPITestHarness):
watt_dist = openmc.stats.Watt()
settings_file.source = openmc.source.Source(space=uniform_dist,
energy=watt_dist)
settings_file.export_to_xml()
self._model.settings = settings_file
# Create tallies
tallies = openmc.Tallies()
tally = openmc.Tally(1)
tally.scores = ['flux']
tallies.append(tally)
tallies.export_to_xml()
self._model.tallies = tallies
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
@ -66,5 +65,6 @@ class CreateFissionNeutronsTestHarness(PyAPITestHarness):
def test_create_fission_neutrons():
harness = CreateFissionNeutronsTestHarness('statepoint.10.h5')
harness = CreateFissionNeutronsTestHarness('statepoint.10.h5',
model=openmc.Model())
harness.main()

View file

@ -1,40 +1,39 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<dagmc_universe filename="dagmc.h5m" id="1" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="40" name="no-void fuel">
<density units="g/cc" value="11" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="41" name="water">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
<temperature_default>293</temperature_default>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="40" name="no-void fuel">
<density units="g/cc" value="11" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="41" name="water">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<dagmc_universe filename="dagmc.h5m" id="1" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
<temperature_default>293</temperature_default>
</settings>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
</model>

View file

@ -1,39 +1,38 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<dagmc_universe filename="dagmc.h5m" id="1" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="40" name="no-void fuel">
<density units="g/cc" value="11" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="41" name="water">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="40" name="no-void fuel">
<density units="g/cc" value="11" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="41" name="water">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<dagmc_universe filename="dagmc.h5m" id="1" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
</model>

View file

@ -1,29 +1,28 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<dagmc_universe auto_geom_ids="true" filename="dagmc.h5m" id="9" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="cell">
<bins>2</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
<model>
<materials>
</materials>
<geometry>
<dagmc_universe auto_geom_ids="true" filename="dagmc.h5m" id="1" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="cell">
<bins>2</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
</model>

View file

@ -10,34 +10,29 @@ pytestmark = pytest.mark.skipif(
reason="DAGMC CAD geometry is not enabled.")
class UWUWTest(PyAPITestHarness):
def _build_inputs(self):
model = openmc.model.Model()
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
# settings
model.settings.batches = 5
model.settings.inactive = 0
model.settings.particles = 100
self._model.settings.batches = 5
self._model.settings.inactive = 0
self._model.settings.particles = 100
source = openmc.Source(space=Box([-4, -4, -4],
[ 4, 4, 4]))
model.settings.source = source
model.settings.export_to_xml()
self._model.settings.source = source
# geometry
dag_univ = openmc.DAGMCUniverse("dagmc.h5m", auto_geom_ids=True)
model.geometry = openmc.Geometry(dag_univ)
self._model.geometry = openmc.Geometry(dag_univ)
# tally
tally = openmc.Tally()
tally.scores = ['total']
tally.filters = [openmc.CellFilter(2)]
model.tallies = [tally]
self._model.tallies = [tally]
model.tallies.export_to_xml()
model.export_to_xml()
def test_refl():
harness = UWUWTest('statepoint.5.h5')
harness = UWUWTest('statepoint.5.h5', model=openmc.Model())
harness.main()

View file

@ -1,55 +1,55 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="12" id="13" region="9 -10 11 -12 13 -14" universe="13" />
<dagmc_universe auto_geom_ids="true" filename="dagmc.h5m" id="9" />
<lattice id="12">
<pitch>24.0 24.0</pitch>
<dimension>2 2</dimension>
<lower_left>-24.0 -24.0</lower_left>
<universes>
9 9
9 9 </universes>
</lattice>
<surface boundary="reflective" coeffs="-24.0" id="9" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="24.0" id="10" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-24.0" id="11" name="front" type="y-plane" />
<surface boundary="reflective" coeffs="24.0" id="12" name="back" type="y-plane" />
<surface boundary="reflective" coeffs="-10.0" id="13" name="bottom" type="z-plane" />
<surface boundary="reflective" coeffs="10.0" id="14" name="top" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="13" name="no-void fuel">
<density units="g/cc" value="10.29769" />
<nuclide ao="0.93120485" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="14" name="clad">
<density units="g/cc" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="15" name="water">
<density units="g/cc" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>2</inactive>
<output>
<summary>false</summary>
</output>
</settings>
<model>
<materials>
<material depletable="true" id="1" name="no-void fuel">
<density units="g/cc" value="10.29769" />
<nuclide ao="0.93120485" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="clad">
<density units="g/cc" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="water">
<density units="g/cc" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell fill="4" id="1" region="1 -2 3 -4 5 -6" universe="5" />
<dagmc_universe auto_geom_ids="true" filename="dagmc.h5m" id="1" />
<lattice id="4">
<pitch>24.0 24.0</pitch>
<dimension>2 2</dimension>
<lower_left>-24.0 -24.0</lower_left>
<universes>
1 1
1 1 </universes>
</lattice>
<surface boundary="reflective" coeffs="-24.0" id="1" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="24.0" id="2" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-24.0" id="3" name="front" type="y-plane" />
<surface boundary="reflective" coeffs="24.0" id="4" name="back" type="y-plane" />
<surface boundary="reflective" coeffs="-10.0" id="5" name="bottom" type="z-plane" />
<surface boundary="reflective" coeffs="10.0" id="6" name="top" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>2</inactive>
<output>
<summary>false</summary>
</output>
</settings>
</model>

View file

@ -12,9 +12,8 @@ pytestmark = pytest.mark.skipif(
class DAGMCUniverseTest(PyAPITestHarness):
def _build_inputs(self):
model = openmc.model.Model()
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
### MATERIALS ###
fuel = openmc.Material(name='no-void fuel')
@ -40,7 +39,7 @@ class DAGMCUniverseTest(PyAPITestHarness):
water.add_nuclide('B11', 3.2218e-05)
water.add_s_alpha_beta('c_H_in_H2O')
model.materials = openmc.Materials([fuel, cladding, water])
self._model.materials = openmc.Materials([fuel, cladding, water])
### GEOMETRY ###
# create the DAGMC universe
@ -51,7 +50,7 @@ class DAGMCUniverseTest(PyAPITestHarness):
# uses the bound_dag_cell as the root argument to test the type checks in openmc.Geometry
bound_pincell_geometry = openmc.Geometry(root=bound_pincell_universe)
# assigns the bound_dag_geometry to the model to test the type checks in model.Geometry setter
model.Geometry = bound_pincell_geometry
self._model.geometry = bound_pincell_geometry
# create a 2 x 2 lattice using the DAGMC pincell
pitch = np.asarray((24.0, 24.0))
@ -71,17 +70,15 @@ class DAGMCUniverseTest(PyAPITestHarness):
bounding_region = +left & -right & +front & -back & +bottom & -top
bounding_cell = openmc.Cell(fill=lattice, region=bounding_region)
model.geometry = openmc.Geometry([bounding_cell])
self._model.geometry = openmc.Geometry([bounding_cell])
# settings
model.settings.particles = 100
model.settings.batches = 10
model.settings.inactive = 2
model.settings.output = {'summary' : False}
model.export_to_xml()
self._model.settings.particles = 100
self._model.settings.batches = 10
self._model.settings.inactive = 2
self._model.settings.output = {'summary' : False}
def test_univ():
harness = DAGMCUniverseTest('statepoint.10.h5')
harness = DAGMCUniverseTest('statepoint.10.h5', model=openmc.Model())
harness.main()

View file

@ -1,29 +1,28 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<dagmc_universe filename="dagmc.h5m" id="9" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
<model>
<materials>
</materials>
<geometry>
<dagmc_universe filename="dagmc.h5m" id="1" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
</model>

View file

@ -10,33 +10,29 @@ pytestmark = pytest.mark.skipif(
reason="DAGMC CAD geometry is not enabled.")
class UWUWTest(PyAPITestHarness):
def _build_inputs(self):
model = openmc.model.Model()
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
# settings
model.settings.batches = 5
model.settings.inactive = 0
model.settings.particles = 100
self._model.settings.batches = 5
self._model.settings.inactive = 0
self._model.settings.particles = 100
source = openmc.Source(space=Box([-4, -4, -4],
[ 4, 4, 4]))
model.settings.source = source
model.settings.export_to_xml()
self._model.settings.source = source
# geometry
dag_univ = openmc.DAGMCUniverse("dagmc.h5m")
model.geometry = openmc.Geometry(root=dag_univ)
self._model.geometry = openmc.Geometry(root=dag_univ)
# tally
tally = openmc.Tally()
tally.scores = ['total']
tally.filters = [openmc.CellFilter(1)]
model.tallies = [tally]
self._model.tallies = [tally]
model.export_to_xml()
def test_uwuw():
harness = UWUWTest('statepoint.5.h5')
harness = UWUWTest('statepoint.5.h5', model=openmc.Model())
harness.main()

View file

@ -1,38 +1,187 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
<model>
<materials>
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector / Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
@ -50,12 +199,12 @@
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
@ -73,12 +222,12 @@
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
@ -100,12 +249,12 @@
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
@ -127,313 +276,163 @@
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector / Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>3</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<temperature_multipole>true</temperature_multipole>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="material">
<bins>1 3</bins>
</filter>
<filter id="2" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
<derivative>1</derivative>
</tally>
<tally id="2">
<filters>1</filters>
<scores>flux</scores>
<derivative>2</derivative>
</tally>
<tally id="3">
<filters>1</filters>
<scores>flux</scores>
<derivative>3</derivative>
</tally>
<tally id="4">
<filters>1</filters>
<scores>flux</scores>
<derivative>4</derivative>
</tally>
<tally id="5">
<filters>1</filters>
<scores>flux</scores>
<derivative>5</derivative>
</tally>
<tally id="6">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>1</derivative>
</tally>
<tally id="7">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>2</derivative>
</tally>
<tally id="8">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>3</derivative>
</tally>
<tally id="9">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>4</derivative>
</tally>
<tally id="10">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>5</derivative>
</tally>
<tally id="11">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>1</derivative>
</tally>
<tally id="12">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>2</derivative>
</tally>
<tally id="13">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>3</derivative>
</tally>
<tally id="14">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>4</derivative>
</tally>
<tally id="15">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>5</derivative>
</tally>
<tally id="16">
<filters>1 2</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>1</derivative>
</tally>
<tally id="17">
<filters>1 2</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>2</derivative>
</tally>
<tally id="18">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>3</derivative>
</tally>
<tally id="19">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>4</derivative>
</tally>
<tally id="20">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>5</derivative>
</tally>
<derivative id="1" material="3" variable="density" />
<derivative id="2" material="1" variable="density" />
<derivative id="3" material="1" nuclide="O16" variable="nuclide_density" />
<derivative id="4" material="1" nuclide="U235" variable="nuclide_density" />
<derivative id="5" material="1" variable="temperature" />
</tallies>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>3</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<temperature_multipole>true</temperature_multipole>
</settings>
<tallies>
<filter id="1" type="material">
<bins>1 3</bins>
</filter>
<filter id="2" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
<derivative>1</derivative>
</tally>
<tally id="2">
<filters>1</filters>
<scores>flux</scores>
<derivative>2</derivative>
</tally>
<tally id="3">
<filters>1</filters>
<scores>flux</scores>
<derivative>3</derivative>
</tally>
<tally id="4">
<filters>1</filters>
<scores>flux</scores>
<derivative>4</derivative>
</tally>
<tally id="5">
<filters>1</filters>
<scores>flux</scores>
<derivative>5</derivative>
</tally>
<tally id="6">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>1</derivative>
</tally>
<tally id="7">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>2</derivative>
</tally>
<tally id="8">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>3</derivative>
</tally>
<tally id="9">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>4</derivative>
</tally>
<tally id="10">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>5</derivative>
</tally>
<tally id="11">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>1</derivative>
</tally>
<tally id="12">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>2</derivative>
</tally>
<tally id="13">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>3</derivative>
</tally>
<tally id="14">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>4</derivative>
</tally>
<tally id="15">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>5</derivative>
</tally>
<tally id="16">
<filters>1 2</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>1</derivative>
</tally>
<tally id="17">
<filters>1 2</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>2</derivative>
</tally>
<tally id="18">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>3</derivative>
</tally>
<tally id="19">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>4</derivative>
</tally>
<tally id="20">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>5</derivative>
</tally>
<derivative id="1" material="3" variable="density" />
<derivative id="2" material="1" variable="density" />
<derivative id="3" material="1" nuclide="O16" variable="nuclide_density" />
<derivative id="4" material="1" nuclide="U235" variable="nuclide_density" />
<derivative id="5" material="1" variable="temperature" />
</tallies>
</model>

View file

@ -1,62 +1,61 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" universe="1" />
<cell id="11" material="2 void 3 2" region="-9" universe="11" />
<cell id="12" material="1" region="9" universe="11" />
<cell fill="101" id="101" region="10 -11 12 -13" universe="0" />
<lattice id="101">
<pitch>2.0 2.0</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<universes>
<model>
<materials>
<material id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="3">
<density units="g/cc" value="2.0" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<geometry>
<cell id="1" material="1" universe="1" />
<cell id="11" material="2 void 3 2" region="-1" universe="11" />
<cell id="12" material="1" region="1" universe="11" />
<cell fill="101" id="101" region="2 -3 4 -5" universe="0" />
<lattice id="101">
<pitch>2.0 2.0</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<universes>
11 11
11 11 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.3" id="9" type="z-cylinder" />
<surface boundary="reflective" coeffs="-3.0" id="10" type="x-plane" />
<surface boundary="reflective" coeffs="3.0" id="11" type="x-plane" />
<surface boundary="reflective" coeffs="-3.0" id="12" type="y-plane" />
<surface boundary="reflective" coeffs="3.0" id="13" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="3">
<density units="g/cc" value="2.0" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<plots>
<plot basis="xy" color_by="cell" filename="cellplot" id="1" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
<plot basis="xy" color_by="material" filename="matplot" id="2" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
</plots>
</lattice>
<surface coeffs="0.0 0.0 0.3" id="1" type="z-cylinder" />
<surface boundary="reflective" coeffs="-3.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="3.0" id="3" type="x-plane" />
<surface boundary="reflective" coeffs="-3.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="3.0" id="5" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>
<plots>
<plot basis="xy" color_by="cell" filename="cellplot" id="1" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
<plot basis="xy" color_by="material" filename="matplot" id="2" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
</plots>
</model>

View file

@ -4,7 +4,7 @@ Cell
ID = 11
Name =
Fill = [2, None, 3, 2]
Region = -9
Region = -1
Rotation = None
Translation = None
Volume = None

View file

@ -4,7 +4,8 @@ from tests.testing_harness import TestHarness, PyAPITestHarness
class DistribmatTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
####################
# Materials
####################
@ -22,8 +23,8 @@ class DistribmatTestHarness(PyAPITestHarness):
light_fuel.set_density('g/cc', 2.0)
light_fuel.add_nuclide('U235', 1.0)
mats_file = openmc.Materials([moderator, dense_fuel, light_fuel])
mats_file.export_to_xml()
self._model.materials = openmc.Materials([moderator, dense_fuel,
light_fuel])
####################
# Geometry
@ -54,8 +55,7 @@ class DistribmatTestHarness(PyAPITestHarness):
c101.region = +x0 & -x1 & +y0 & -y1
root_univ = openmc.Universe(universe_id=0, cells=[c101])
geometry = openmc.Geometry(root_univ)
geometry.export_to_xml()
self._model.geometry = openmc.Geometry(root_univ)
####################
# Settings
@ -67,7 +67,7 @@ class DistribmatTestHarness(PyAPITestHarness):
sets_file.particles = 1000
sets_file.source = openmc.Source(space=openmc.stats.Box(
[-1, -1, -1], [1, 1, 1]))
sets_file.export_to_xml()
self._model.settings = sets_file
####################
# Plots
@ -89,8 +89,7 @@ class DistribmatTestHarness(PyAPITestHarness):
plot2.width = (7, 7)
plot2.pixels = (400, 400)
plots = openmc.Plots([plot1, plot2])
plots.export_to_xml()
self._model.plots = openmc.Plots([plot1, plot2])
def _get_results(self):
outstr = super()._get_results()
@ -100,5 +99,5 @@ class DistribmatTestHarness(PyAPITestHarness):
def test_distribmat():
harness = DistribmatTestHarness('statepoint.5.h5')
harness = DistribmatTestHarness('statepoint.5.h5', model=openmc.Model())
harness.main()

View file

@ -1,31 +1,30 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 10.0" id="1" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>7</batches>
<inactive>3</inactive>
<generations_per_batch>3</generations_per_batch>
<source strength="1.0">
<space type="box">
<parameters>-4.0 -4.0 -4.0 4.0 4.0 4.0</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="1">
<scores>flux</scores>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 10.0" id="1" type="sphere" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>7</batches>
<inactive>3</inactive>
<generations_per_batch>3</generations_per_batch>
<source strength="1.0">
<space type="box">
<parameters>-4.0 -4.0 -4.0 4.0 4.0 4.0</parameters>
</space>
</source>
</settings>
<tallies>
<tally id="1">
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,42 +1,41 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0" />
<surface boundary="reflective" coeffs="-1" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="1" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<cutoff>
<energy_neutron>4.0</energy_neutron>
</cutoff>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="energy">
<bins>0.0 4.0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
<model>
<materials>
<material id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0" />
<surface boundary="reflective" coeffs="-1" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="1" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<cutoff>
<energy_neutron>4.0</energy_neutron>
</cutoff>
</settings>
<tallies>
<filter id="1" type="energy">
<bins>0.0 4.0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -4,7 +4,8 @@ from tests.testing_harness import PyAPITestHarness
class EnergyCutoffTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
# Set energy cutoff
energy_cutoff = 4.0
@ -12,8 +13,7 @@ class EnergyCutoffTestHarness(PyAPITestHarness):
mat = openmc.Material(material_id=1, name='mat')
mat.set_density('atom/b-cm', 0.069335)
mat.add_nuclide('H1', 40.0)
materials_file = openmc.Materials([mat])
materials_file.export_to_xml()
self._model.materials = openmc.Materials([mat])
# Cell is box with reflective boundary
x1 = openmc.XPlane(surface_id=1, x0=-1)
@ -29,8 +29,7 @@ class EnergyCutoffTestHarness(PyAPITestHarness):
box.fill = mat
root = openmc.Universe(universe_id=0, name='root universe')
root.add_cell(box)
geometry = openmc.Geometry(root)
geometry.export_to_xml()
self._model.geometry = openmc.Geometry(root)
# Set the running parameters
settings_file = openmc.Settings()
@ -43,7 +42,7 @@ class EnergyCutoffTestHarness(PyAPITestHarness):
watt_dist = openmc.stats.Watt()
settings_file.source = openmc.source.Source(space=uniform_dist,
energy=watt_dist)
settings_file.export_to_xml()
self._model.settings = settings_file
# Tally flux under energy cutoff
tallies = openmc.Tallies()
@ -52,7 +51,7 @@ class EnergyCutoffTestHarness(PyAPITestHarness):
energy_filter = openmc.filter.EnergyFilter((0.0, energy_cutoff))
tally.filters = [energy_filter]
tallies.append(tally)
tallies.export_to_xml()
self._model.tallies = tallies
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
@ -70,5 +69,5 @@ class EnergyCutoffTestHarness(PyAPITestHarness):
def test_energy_cutoff():
harness = EnergyCutoffTestHarness('statepoint.10.h5')
harness = EnergyCutoffTestHarness('statepoint.10.h5', model=openmc.Model())
harness.main()

View file

@ -1,23 +1,23 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="reflective" coeffs="0.0 0.0 0.0 100.0" id="1" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="20.0" />
<nuclide ao="1.0" name="U233" />
<nuclide ao="1.0" name="Am244" />
<nuclide ao="1.0" name="H2" />
<nuclide ao="1.0" name="Na23" />
<nuclide ao="1.0" name="Ta181" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
</settings>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="20.0" />
<nuclide ao="1.0" name="U233" />
<nuclide ao="1.0" name="Am244" />
<nuclide ao="1.0" name="H2" />
<nuclide ao="1.0" name="Na23" />
<nuclide ao="1.0" name="Ta181" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="reflective" coeffs="0.0 0.0 0.0 100.0" id="1" type="sphere" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
</settings>
</model>

View file

@ -1,73 +1,72 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="point">
<parameters>0.0 0.0 0.0</parameters>
</space>
<angle reference_uvw="-1.0 0.0 0.0" type="monodirectional" />
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" library="moab" type="unstructured">
<filename>test_mesh_tets.h5m</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1" name="unstructured mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="point">
<parameters>0.0 0.0 0.0</parameters>
</space>
<angle reference_uvw="-1.0 0.0 0.0" type="monodirectional" />
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1" library="moab" type="unstructured">
<filename>test_mesh_tets.h5m</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1" name="unstructured mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
</model>

View file

@ -162,8 +162,6 @@ def test_external_mesh(cpp_driver):
water_mat.set_density("atom/b-cm", 0.07416)
materials.append(water_mat)
materials.export_to_xml()
# Geometry
fuel_min_x = openmc.XPlane(-5.0, name="minimum x")
fuel_max_x = openmc.XPlane(5.0, name="maximum x")

View file

@ -1,65 +1,64 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="2" />
<cell id="2" material="2" region="1" universe="1" />
<cell fill="1" id="3" universe="2" />
<cell id="4" material="1" region="-2" universe="3" />
<cell id="5" material="2" region="2" universe="3" />
<cell fill="4" id="6" region="3 -4 5 -6" universe="5" />
<lattice id="4">
<pitch>2 2</pitch>
<dimension>4 4</dimension>
<lower_left>-4 -4</lower_left>
<universes>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="H1" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="2" />
<cell id="2" material="2" region="1" universe="1" />
<cell fill="1" id="3" universe="2" />
<cell id="4" material="1" region="-2" universe="3" />
<cell id="5" material="2" region="2" universe="3" />
<cell fill="4" id="6" region="3 -4 5 -6" universe="5" />
<lattice id="4">
<pitch>2 2</pitch>
<dimension>4 4</dimension>
<lower_left>-4 -4</lower_left>
<universes>
2 3 3 3
3 2 3 3
3 3 2 3
3 3 3 2 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.7" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.5" id="2" type="z-cylinder" />
<surface boundary="reflective" coeffs="-4.0" id="3" name="minimum x" type="x-plane" />
<surface boundary="reflective" coeffs="4.0" id="4" name="maximum x" type="x-plane" />
<surface boundary="reflective" coeffs="-4.0" id="5" name="minimum y" type="y-plane" />
<surface boundary="reflective" coeffs="4.0" id="6" name="maximum y" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="H1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="point">
<parameters>0.0 0.0 0.0</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="cellinstance">
<bins>4 0 4 1 4 2 4 3 4 4 4 5 4 6 4 7 4 8 4 9 4 10 4 11 2 0 2 1 2 2 2 3 3 0 3 1 3 2 3 3</bins>
</filter>
<filter id="2" type="cellinstance">
<bins>3 3 3 2 3 1 3 0 2 3 2 2 2 1 2 0 4 11 4 10 4 9 4 8 4 7 4 6 4 5 4 4 4 3 4 2 4 1 4 0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
<tally id="2">
<filters>2</filters>
<scores>total</scores>
</tally>
</tallies>
</lattice>
<surface coeffs="0.0 0.0 0.7" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.5" id="2" type="z-cylinder" />
<surface boundary="reflective" coeffs="-4.0" id="3" name="minimum x" type="x-plane" />
<surface boundary="reflective" coeffs="4.0" id="4" name="maximum x" type="x-plane" />
<surface boundary="reflective" coeffs="-4.0" id="5" name="minimum y" type="y-plane" />
<surface boundary="reflective" coeffs="4.0" id="6" name="maximum y" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="point">
<parameters>0.0 0.0 0.0</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="cellinstance">
<bins>4 0 4 1 4 2 4 3 4 4 4 5 4 6 4 7 4 8 4 9 4 10 4 11 2 0 2 1 2 2 2 3 3 0 3 1 3 2 3 3</bins>
</filter>
<filter id="2" type="cellinstance">
<bins>3 3 3 2 3 1 3 0 2 3 2 2 2 1 2 0 4 11 4 10 4 9 4 8 4 7 4 6 4 5 4 4 4 3 4 2 4 1 4 0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
<tally id="2">
<filters>2</filters>
<scores>total</scores>
</tally>
</tallies>
</model>

View file

@ -1,106 +1,105 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 100.0" id="1" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="Am241" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="energyfunction">
<energy>1e-05 0.369 1000.0 100000.0 600000.0 1000000.0 2000000.0 4000000.0 30000000.0</energy>
<y>0.1 0.1 0.1333 0.158 0.18467 0.25618 0.4297 0.48 0.48</y>
<interpolation>linear-linear</interpolation>
</filter>
<filter id="3" type="energyfunction">
<energy>1e-05 0.369 1000.0 100000.0 600000.0 1000000.0 2000000.0 4000000.0 30000000.0</energy>
<y>0.1 0.1 0.1333 0.158 0.18467 0.25618 0.4297 0.48 0.48</y>
<interpolation>log-log</interpolation>
</filter>
<filter id="4" type="energyfunction">
<energy>1e-05 0.369 1000.0 100000.0 600000.0 1000000.0 2000000.0 4000000.0 30000000.0</energy>
<y>0.1 0.1 0.1333 0.158 0.18467 0.25618 0.4297 0.48 0.48</y>
<interpolation>linear-log</interpolation>
</filter>
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View file

@ -1,152 +1,151 @@
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View file

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<?xml version='1.0' encoding='utf-8'?>
<materials>
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<?xml version='1.0' encoding='utf-8'?>
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<filter id="1" type="mesh">
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</tally>
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<model>
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View file

@ -1,31 +1,30 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
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<tally id="1">
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</tally>
</tallies>
</model>

View file

@ -1,38 +1,199 @@
<?xml version='1.0' encoding='utf-8'?>
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<model>
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<isotropic>H1 O16 B10 B11 Fe54 Fe56 Fe57 Fe58 Ni58 Mn55 Cr52</isotropic>
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<material id="12" name="Bottom of fuel assemblies">
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
@ -50,12 +211,12 @@
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
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<lattice id="101" name="Fuel assembly (upper half)">
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<universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
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<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
@ -73,12 +234,12 @@
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
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5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
@ -100,12 +261,12 @@
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
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<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
@ -127,195 +288,34 @@
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
<isotropic>U234 U235 U238 Xe135 O16</isotropic>
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
<isotropic>Zr90 Zr91 Zr92 Zr94 Zr96</isotropic>
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
<isotropic>H1 O16 B10 B11</isotropic>
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
<isotropic>H1 O16 B10 B11</isotropic>
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
<isotropic>Fe54 Fe56 Fe57 Fe58 Ni58 Ni60 Mn55 Cr52 C0 Cu63</isotropic>
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
<isotropic>H1 O16 B10 B11 Fe54 Fe56 Fe57 Fe58 Ni58 Mn55 Cr52</isotropic>
</material>
<material id="7" name="Upper radial reflector / Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
<isotropic>H1 O16 B10 B11 Fe54 Fe56 Fe57 Fe58 Ni58 Mn55 Cr52</isotropic>
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
<isotropic>H1 O16 B10 B11 Fe54 Fe56 Fe57 Fe58 Ni58 Mn55 Cr52</isotropic>
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
<isotropic>H1 O16 B10 B11 Fe54 Fe56 Fe57 Fe58 Ni58 Mn55 Cr52</isotropic>
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
<isotropic>H1 O16 B10 B11 Fe54 Fe56 Fe57 Fe58 Ni58 Mn55 Cr52</isotropic>
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
<isotropic>H1 O16 B10 B11 Zr90 Zr91 Zr92 Zr94 Zr96</isotropic>
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
<isotropic>H1 O16 B10 B11 Zr90 Zr91 Zr92 Zr94 Zr96</isotropic>
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
</settings>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
</settings>
</model>

View file

@ -1,81 +1,81 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="13" material="13" region="-9 10 -11" universe="9" />
<cell id="14" material="14" region="9" universe="9" />
<cell id="15" material="16" name="coolant" region="-12 10 -11" universe="10" />
<cell id="16" material="17" name="zirconium_shell" region="12 -13 10 -11" universe="10" />
<cell id="17" material="15" name="lead_shell" region="13 -14 10 -11" universe="10" />
<cell id="18" material="14" name="matrix coolant surround" region="14 10 -11" universe="10" />
<cell id="19" material="14" universe="11" />
<cell fill="12" id="20" name="container cell" region="-15 16 -17 18 19 -20 10 -11" universe="13" />
<hex_lattice id="12" n_rings="2" name="regular fuel assembly">
<pitch>1.4</pitch>
<outer>11</outer>
<center>0.0 0.0</center>
<universes>
10
10 10
9
10 10
10</universes>
</hex_lattice>
<surface coeffs="0.0 0.0 0.7" id="9" type="z-cylinder" />
<surface boundary="reflective" coeffs="0.0" id="10" type="z-plane" />
<surface boundary="reflective" coeffs="10.0" id="11" type="z-plane" />
<surface coeffs="0.0 0.0 0.293" id="12" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.35" id="13" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.352" id="14" type="z-cylinder" />
<surface boundary="reflective" coeffs="1.4" id="15" type="y-plane" />
<surface boundary="reflective" coeffs="-1.4" id="16" type="y-plane" />
<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 2.8" id="17" type="plane" />
<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 -2.8" id="18" type="plane" />
<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 -2.8" id="19" type="plane" />
<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 2.8" id="20" type="plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="13">
<density units="sum" />
<nuclide ao="0.0049817" name="U235" />
</material>
<material id="14">
<density units="atom/b-cm" value="0.017742" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
<material id="15" name="Lead">
<density units="g/cm3" value="10.32" />
<nuclide ao="0.014" name="Pb204" />
<nuclide ao="0.241" name="Pb206" />
<nuclide ao="0.221" name="Pb207" />
<nuclide ao="0.524" name="Pb208" />
</material>
<material id="16">
<density units="atom/b-cm" value="0.00054464" />
<nuclide ao="1.0" name="He4" />
</material>
<material id="17" name="Zirc4">
<density units="sum" />
<nuclide ao="0.02217" name="Zr90" />
<nuclide ao="0.004781" name="Zr91" />
<nuclide ao="0.007228" name="Zr92" />
<nuclide ao="0.007169" name="Zr94" />
<nuclide ao="0.001131" name="Zr96" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>2</inactive>
<source strength="1.0">
<space type="box">
<parameters>-0.9899494936611666 -0.9899494936611666 0.0 0.9899494936611666 0.9899494936611666 10.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<seed>22</seed>
</settings>
<model>
<materials>
<material depletable="true" id="1">
<density units="sum" />
<nuclide ao="0.0049817" name="U235" />
</material>
<material id="2">
<density units="atom/b-cm" value="0.017742" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
<material id="3" name="Lead">
<density units="g/cm3" value="10.32" />
<nuclide ao="0.014" name="Pb204" />
<nuclide ao="0.241" name="Pb206" />
<nuclide ao="0.221" name="Pb207" />
<nuclide ao="0.524" name="Pb208" />
</material>
<material id="4">
<density units="atom/b-cm" value="0.00054464" />
<nuclide ao="1.0" name="He4" />
</material>
<material id="5" name="Zirc4">
<density units="sum" />
<nuclide ao="0.02217" name="Zr90" />
<nuclide ao="0.004781" name="Zr91" />
<nuclide ao="0.007228" name="Zr92" />
<nuclide ao="0.007169" name="Zr94" />
<nuclide ao="0.001131" name="Zr96" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3" universe="1" />
<cell id="2" material="2" region="1" universe="1" />
<cell id="3" material="4" name="coolant" region="-4 2 -3" universe="2" />
<cell id="4" material="5" name="zirconium_shell" region="4 -5 2 -3" universe="2" />
<cell id="5" material="3" name="lead_shell" region="5 -6 2 -3" universe="2" />
<cell id="6" material="2" name="matrix coolant surround" region="6 2 -3" universe="2" />
<cell id="7" material="2" universe="3" />
<cell fill="4" id="8" name="container cell" region="-7 8 -9 10 11 -12 2 -3" universe="5" />
<hex_lattice id="4" n_rings="2" name="regular fuel assembly">
<pitch>1.4</pitch>
<outer>3</outer>
<center>0.0 0.0</center>
<universes>
2
2 2
1
2 2
2</universes>
</hex_lattice>
<surface coeffs="0.0 0.0 0.7" id="1" type="z-cylinder" />
<surface boundary="reflective" coeffs="0.0" id="2" type="z-plane" />
<surface boundary="reflective" coeffs="10.0" id="3" type="z-plane" />
<surface coeffs="0.0 0.0 0.293" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.35" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.352" id="6" type="z-cylinder" />
<surface boundary="reflective" coeffs="1.4" id="7" type="y-plane" />
<surface boundary="reflective" coeffs="-1.4" id="8" type="y-plane" />
<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 2.8" id="9" type="plane" />
<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 -2.8" id="10" type="plane" />
<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 -2.8" id="11" type="plane" />
<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 2.8" id="12" type="plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>2</inactive>
<source strength="1.0">
<space type="box">
<parameters>-0.9899494936611666 -0.9899494936611666 0.0 0.9899494936611666 0.9899494936611666 10.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<seed>22</seed>
</settings>
</model>

View file

@ -6,7 +6,8 @@ from tests.testing_harness import PyAPITestHarness
class HexLatticeCoincidentTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
materials = openmc.Materials()
fuel_mat = openmc.Material()
@ -40,7 +41,7 @@ class HexLatticeCoincidentTestHarness(PyAPITestHarness):
zirc.add_nuclide('Zr96', 1.131E-03, 'ao')
materials.append(zirc)
materials.export_to_xml()
self._model.materials = materials
### Geometry ###
pin_rad = 0.7 # cm
@ -124,8 +125,7 @@ class HexLatticeCoincidentTestHarness(PyAPITestHarness):
root_univ = openmc.Universe(name="root universe", cells=[pincell_only_cell,])
geom = openmc.Geometry(root_univ)
geom.export_to_xml()
self._model.geometry = openmc.Geometry(root_univ)
### Settings ###
@ -144,8 +144,9 @@ class HexLatticeCoincidentTestHarness(PyAPITestHarness):
settings.inactive = 2
settings.particles = 1000
settings.seed = 22
settings.export_to_xml()
self._model.settings = settings
def test_lattice_hex_coincident_surf():
harness = HexLatticeCoincidentTestHarness('statepoint.5.h5')
harness = HexLatticeCoincidentTestHarness('statepoint.5.h5',
model=openmc.Model())
harness.main()

View file

@ -1,23 +1,53 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="4" region="-2 1" universe="1" />
<cell id="3" material="2" region="2" universe="1" />
<cell id="4" material="2" region="-3" universe="2" />
<cell id="5" material="4" region="-4 3" universe="2" />
<cell id="6" material="2" region="4" universe="2" />
<cell id="7" material="3" region="-5" universe="3" />
<cell id="8" material="4" region="-6 5" universe="3" />
<cell id="9" material="2" region="-7 6" universe="3" />
<cell id="10" material="4" region="-8 7" universe="3" />
<cell id="11" material="2" region="8" universe="3" />
<cell id="12" material="2" universe="4" />
<cell fill="9" id="13" name="container assembly cell" region="-11 12 -13 14 15 -16 9 -10" universe="5" />
<hex_lattice id="9" n_axial="2" n_rings="11" name="regular fuel assembly" orientation="x">
<pitch>1.235 5.0</pitch>
<outer>4</outer>
<center>0.0 0.0 5.0</center>
<universes>
<model>
<materials>
<material depletable="true" id="1" name="UO2">
<density units="sum" />
<nuclide ao="0.0008737" name="U235" />
<nuclide ao="0.018744" name="U238" />
<nuclide ao="0.039235" name="O16" />
</material>
<material id="2" name="borated H2O">
<density units="sum" />
<nuclide ao="0.06694" name="H1" />
<nuclide ao="0.03347" name="O16" />
<nuclide ao="6.6262e-06" name="B10" />
<nuclide ao="2.6839e-05" name="B11" />
</material>
<material id="3" name="pellet B4C">
<density units="sum" />
<nuclide ao="0.01966" name="C0" />
<nuclide ao="4.7344e-06" name="B11" />
<nuclide ao="1.9177e-05" name="B10" />
</material>
<material id="4" name="Zirc4">
<density units="sum" />
<nuclide ao="0.021763349999999997" name="Zr90" />
<nuclide ao="0.00474606" name="Zr91" />
<nuclide ao="0.00725445" name="Zr92" />
<nuclide ao="0.00735174" name="Zr94" />
<nuclide ao="0.0011844" name="Zr96" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="4" region="-2 1" universe="1" />
<cell id="3" material="2" region="2" universe="1" />
<cell id="4" material="2" region="-3" universe="2" />
<cell id="5" material="4" region="-4 3" universe="2" />
<cell id="6" material="2" region="4" universe="2" />
<cell id="7" material="3" region="-5" universe="3" />
<cell id="8" material="4" region="-6 5" universe="3" />
<cell id="9" material="2" region="-7 6" universe="3" />
<cell id="10" material="4" region="-8 7" universe="3" />
<cell id="11" material="2" region="8" universe="3" />
<cell id="12" material="2" universe="4" />
<cell fill="6" id="13" name="container assembly cell" region="-11 12 -13 14 15 -16 9 -10" universe="5" />
<hex_lattice id="6" n_axial="2" n_rings="11" name="regular fuel assembly" orientation="x">
<pitch>1.235 5.0</pitch>
<outer>4</outer>
<center>0.0 0.0 5.0</center>
<universes>
1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1
@ -60,64 +90,34 @@
1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1</universes>
</hex_lattice>
<surface coeffs="0.0 0.0 0.386" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.4582" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.45" id="3" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.5177" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.35" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.41" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.545" id="7" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.6323" id="8" type="z-cylinder" />
<surface boundary="reflective" coeffs="0.0" id="9" type="z-plane" />
<surface boundary="reflective" coeffs="10.0" id="10" type="z-plane" />
<surface boundary="reflective" coeffs="11.8" id="11" type="y-plane" />
<surface boundary="reflective" coeffs="-11.8" id="12" type="y-plane" />
<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 23.6" id="13" type="plane" />
<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 -23.6" id="14" type="plane" />
<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 -23.6" id="15" type="plane" />
<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 23.6" id="16" type="plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UO2">
<density units="sum" />
<nuclide ao="0.0008737" name="U235" />
<nuclide ao="0.018744" name="U238" />
<nuclide ao="0.039235" name="O16" />
</material>
<material id="2" name="borated H2O">
<density units="sum" />
<nuclide ao="0.06694" name="H1" />
<nuclide ao="0.03347" name="O16" />
<nuclide ao="6.6262e-06" name="B10" />
<nuclide ao="2.6839e-05" name="B11" />
</material>
<material id="3" name="pellet B4C">
<density units="sum" />
<nuclide ao="0.01966" name="C0" />
<nuclide ao="4.7344e-06" name="B11" />
<nuclide ao="1.9177e-05" name="B10" />
</material>
<material id="4" name="Zirc4">
<density units="sum" />
<nuclide ao="0.021763349999999997" name="Zr90" />
<nuclide ao="0.00474606" name="Zr91" />
<nuclide ao="0.00725445" name="Zr92" />
<nuclide ao="0.00735174" name="Zr94" />
<nuclide ao="0.0011844" name="Zr96" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-13.62546635287517 -13.62546635287517 0.0 13.62546635287517 13.62546635287517 10.0</parameters>
</space>
</source>
<seed>22</seed>
</settings>
</hex_lattice>
<surface coeffs="0.0 0.0 0.386" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.4582" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.45" id="3" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.5177" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.35" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.41" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.545" id="7" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.6323" id="8" type="z-cylinder" />
<surface boundary="reflective" coeffs="0.0" id="9" type="z-plane" />
<surface boundary="reflective" coeffs="10.0" id="10" type="z-plane" />
<surface boundary="reflective" coeffs="11.8" id="11" type="y-plane" />
<surface boundary="reflective" coeffs="-11.8" id="12" type="y-plane" />
<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 23.6" id="13" type="plane" />
<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 -23.6" id="14" type="plane" />
<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 -23.6" id="15" type="plane" />
<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 23.6" id="16" type="plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-13.62546635287517 -13.62546635287517 0.0 13.62546635287517 13.62546635287517 10.0</parameters>
</space>
</source>
<seed>22</seed>
</settings>
</model>

View file

@ -4,8 +4,8 @@ import numpy as np
class HexLatticeOXTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
materials = openmc.Materials()
fuel_mat = openmc.Material(material_id=1, name="UO2")
@ -35,7 +35,7 @@ class HexLatticeOXTestHarness(PyAPITestHarness):
zirc.add_element('Zr', 4.23e-2)
materials.append(zirc)
materials.export_to_xml()
self._model.materials = materials
# Geometry #
@ -165,7 +165,7 @@ class HexLatticeOXTestHarness(PyAPITestHarness):
(4, 21), (5, 20), (4, 27), (5, 25), (4, 33)]
for i, j in channels:
universes[i][j] = abs_ch_univ
lattice = openmc.HexLattice(name="regular fuel assembly")
lattice = openmc.HexLattice(lattice_id=6, name="regular fuel assembly")
lattice.orientation = "x"
lattice.center = (0., 0., length/2.0)
lattice.pitch = (assembly_pitch, length/2.0)
@ -180,8 +180,7 @@ class HexLatticeOXTestHarness(PyAPITestHarness):
root_univ = openmc.Universe(universe_id=5, name="root universe",
cells=[assembly_cell])
geom = openmc.Geometry(root_univ)
geom.export_to_xml()
self._model.geometry = openmc.Geometry(root_univ)
# Settings #
@ -198,9 +197,9 @@ class HexLatticeOXTestHarness(PyAPITestHarness):
settings.inactive = 5
settings.particles = 1000
settings.seed = 22
settings.export_to_xml()
self._model.settings = settings
def test_lattice_hex_ox_surf():
harness = HexLatticeOXTestHarness('statepoint.10.h5')
harness = HexLatticeOXTestHarness('statepoint.10.h5', model=openmc.Model())
harness.main()

View file

@ -1,53 +1,53 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="2" region="1" universe="1" />
<cell id="3" material="1" region="-2" universe="2" />
<cell id="4" material="2" region="2" universe="2" />
<cell fill="3" id="5" universe="4" />
<cell fill="5" id="6" region="3 -4 5 -6" universe="6" />
<lattice id="3">
<pitch>1.2 1.2</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-1.2 -1.2</lower_left>
<universes>
<model>
<materials>
<material depletable="true" id="1" name="UO2">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="2.0" name="O16" />
</material>
<material id="2" name="light water">
<density units="g/cm3" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="2" region="1" universe="1" />
<cell id="3" material="1" region="-2" universe="2" />
<cell id="4" material="2" region="2" universe="2" />
<cell fill="3" id="5" universe="4" />
<cell fill="5" id="6" region="3 -4 5 -6" universe="6" />
<lattice id="3">
<pitch>1.2 1.2</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-1.2 -1.2</lower_left>
<universes>
2 1
1 1 </universes>
</lattice>
<lattice id="5">
<pitch>2.4 2.4</pitch>
<dimension>2 2</dimension>
<lower_left>-2.4 -2.4</lower_left>
<universes>
</lattice>
<lattice id="5">
<pitch>2.4 2.4</pitch>
<dimension>2 2</dimension>
<lower_left>-2.4 -2.4</lower_left>
<universes>
4 4
4 4 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.4" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.5" id="2" type="z-cylinder" />
<surface boundary="reflective" coeffs="-2.4" id="3" name="minimum x" type="x-plane" />
<surface boundary="reflective" coeffs="2.4" id="4" name="maximum x" type="x-plane" />
<surface boundary="reflective" coeffs="-2.4" id="5" name="minimum y" type="y-plane" />
<surface boundary="reflective" coeffs="2.4" id="6" name="maximum y" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UO2">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="2.0" name="O16" />
</material>
<material id="2" name="light water">
<density units="g/cm3" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
</settings>
</lattice>
<surface coeffs="0.0 0.0 0.4" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.5" id="2" type="z-cylinder" />
<surface boundary="reflective" coeffs="-2.4" id="3" name="minimum x" type="x-plane" />
<surface boundary="reflective" coeffs="2.4" id="4" name="maximum x" type="x-plane" />
<surface boundary="reflective" coeffs="-2.4" id="5" name="minimum y" type="y-plane" />
<surface boundary="reflective" coeffs="2.4" id="6" name="maximum y" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
</settings>
</model>

View file

@ -1,18 +1,35 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="3" region="1" universe="1" />
<cell id="3" material="2" region="-2" universe="2" />
<cell id="4" material="3" region="2" universe="2" />
<cell id="5" material="3" universe="30" />
<cell fill="4" id="6" region="-3" rotation="0.0 0.0 45.0" translation="-4.0 0.0 0.0" universe="5" />
<cell fill="3" id="7" region="-4" rotation="0.0 0.0 30.0" translation="4.0 0.0 0.0" universe="5" />
<cell id="8" material="3" region="-5 3 4" universe="5" />
<hex_lattice id="3" n_rings="3">
<pitch>1.25</pitch>
<outer>30</outer>
<center>0.0 0.0</center>
<universes>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="2">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="U238" />
</material>
<material id="3">
<density units="g/cm3" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="3" region="1" universe="1" />
<cell id="3" material="2" region="-2" universe="2" />
<cell id="4" material="3" region="2" universe="2" />
<cell id="5" material="3" universe="30" />
<cell fill="4" id="6" region="-3" rotation="0.0 0.0 45.0" translation="-4.0 0.0 0.0" universe="5" />
<cell fill="3" id="7" region="-4" rotation="0.0 0.0 30.0" translation="4.0 0.0 0.0" universe="5" />
<cell id="8" material="3" region="-5 3 4" universe="5" />
<hex_lattice id="3" n_rings="3">
<pitch>1.25</pitch>
<outer>30</outer>
<center>0.0 0.0</center>
<universes>
2
1 1
1 2 1
@ -22,50 +39,33 @@
1 1 1
1 1
1</universes>
</hex_lattice>
<lattice id="4">
<pitch>1.25 1.25</pitch>
<outer>30</outer>
<dimension>4 4</dimension>
<lower_left>-2.5 -2.5</lower_left>
<universes>
</hex_lattice>
<lattice id="4">
<pitch>1.25 1.25</pitch>
<outer>30</outer>
<dimension>4 4</dimension>
<lower_left>-2.5 -2.5</lower_left>
<universes>
2 2 2 2
1 1 1 1
1 1 1 1
1 1 1 1 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.25" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.5" id="2" type="z-cylinder" />
<surface coeffs="-4.0 0.0 4.0" id="3" type="z-cylinder" />
<surface coeffs="4.0 0.0 4.0" id="4" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 8.0" id="5" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="2">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="U238" />
</material>
<material id="3">
<density units="g/cm3" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="point">
<parameters>0.0 0.0 0.0</parameters>
</space>
</source>
</settings>
</lattice>
<surface coeffs="0.0 0.0 0.25" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.5" id="2" type="z-cylinder" />
<surface coeffs="-4.0 0.0 4.0" id="3" type="z-cylinder" />
<surface coeffs="4.0 0.0 4.0" id="4" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 8.0" id="5" type="z-cylinder" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="point">
<parameters>0.0 0.0 0.0</parameters>
</space>
</source>
</settings>
</model>

View file

@ -1,64 +1,64 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<cell id="2" material="2" region="2 -3" universe="0" />
<cell id="3" material="3" region="3 -4" universe="0" />
<cell id="4" material="4" region="4 -5" universe="0" />
<cell id="5" material="5" region="5 -6" universe="0" />
<cell id="6" material="6" region="6 -7" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface coeffs="154.90833333333333" id="2" type="x-plane" />
<surface coeffs="309.81666666666666" id="3" type="x-plane" />
<surface coeffs="464.725" id="4" type="x-plane" />
<surface coeffs="619.6333333333333" id="5" type="x-plane" />
<surface coeffs="774.5416666666666" id="6" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="7" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="base leg">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
<material id="2" name="base tab">
<density units="macro" value="1.0" />
<macroscopic name="mat_2" />
</material>
<material id="3" name="base hist">
<density units="macro" value="1.0" />
<macroscopic name="mat_3" />
</material>
<material id="4" name="base matrix">
<density units="macro" value="1.0" />
<macroscopic name="mat_4" />
</material>
<material id="5" name="base ang">
<density units="macro" value="1.0" />
<macroscopic name="mat_5" />
</material>
<material id="6" name="micro">
<density units="sum" />
<nuclide ao="0.5" name="mat_1" />
<nuclide ao="0.5" name="mat_6" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 154.90833333333333 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
<model>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="base leg">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
<material id="2" name="base tab">
<density units="macro" value="1.0" />
<macroscopic name="mat_2" />
</material>
<material id="3" name="base hist">
<density units="macro" value="1.0" />
<macroscopic name="mat_3" />
</material>
<material id="4" name="base matrix">
<density units="macro" value="1.0" />
<macroscopic name="mat_4" />
</material>
<material id="5" name="base ang">
<density units="macro" value="1.0" />
<macroscopic name="mat_5" />
</material>
<material id="6" name="micro">
<density units="sum" />
<nuclide ao="0.5" name="mat_1" />
<nuclide ao="0.5" name="mat_6" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<cell id="2" material="2" region="2 -3" universe="0" />
<cell id="3" material="3" region="3 -4" universe="0" />
<cell id="4" material="4" region="4 -5" universe="0" />
<cell id="5" material="5" region="5 -6" universe="0" />
<cell id="6" material="6" region="6 -7" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface coeffs="154.90833333333333" id="2" type="x-plane" />
<surface coeffs="309.81666666666666" id="3" type="x-plane" />
<surface coeffs="464.725" id="4" type="x-plane" />
<surface coeffs="619.6333333333333" id="5" type="x-plane" />
<surface coeffs="774.5416666666666" id="6" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="7" type="x-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 154.90833333333333 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
</model>

View file

@ -1,63 +1,63 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<cell id="2" material="2" region="2 -3" universe="0" />
<cell id="3" material="3" region="3 -4" universe="0" />
<cell id="4" material="4" region="4 -5" universe="0" />
<cell id="5" material="5" region="5 -6" universe="0" />
<cell id="6" material="6" region="6 -7" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface coeffs="154.90833333333333" id="2" type="x-plane" />
<surface coeffs="309.81666666666666" id="3" type="x-plane" />
<surface coeffs="464.725" id="4" type="x-plane" />
<surface coeffs="619.6333333333333" id="5" type="x-plane" />
<surface coeffs="774.5416666666666" id="6" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="7" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="vec beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
<material id="2" name="vec no beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_2" />
</material>
<material id="3" name="matrix beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_3" />
</material>
<material id="4" name="matrix no beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_4" />
</material>
<material id="5" name="vec group beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_5" />
</material>
<material id="6" name="matrix group beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_6" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 154.90833333333333 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
<model>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="vec beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
<material id="2" name="vec no beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_2" />
</material>
<material id="3" name="matrix beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_3" />
</material>
<material id="4" name="matrix no beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_4" />
</material>
<material id="5" name="vec group beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_5" />
</material>
<material id="6" name="matrix group beta">
<density units="macro" value="1.0" />
<macroscopic name="mat_6" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<cell id="2" material="2" region="2 -3" universe="0" />
<cell id="3" material="3" region="3 -4" universe="0" />
<cell id="4" material="4" region="4 -5" universe="0" />
<cell id="5" material="5" region="5 -6" universe="0" />
<cell id="6" material="6" region="6 -7" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface coeffs="154.90833333333333" id="2" type="x-plane" />
<surface coeffs="309.81666666666666" id="3" type="x-plane" />
<surface coeffs="464.725" id="4" type="x-plane" />
<surface coeffs="619.6333333333333" id="5" type="x-plane" />
<surface coeffs="774.5416666666666" id="6" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="7" type="x-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 154.90833333333333 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
</model>

View file

@ -1,29 +1,29 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell 1" region="4 -5 6 -7" universe="0" />
<surface boundary="reflective" coeffs="-5.0" id="4" name="left" type="x-plane" />
<surface boundary="vacuum" coeffs="5.0" id="5" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-5.0" id="6" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="5.0" id="7" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>mgxs.h5</cross_sections>
<material id="1" name="UO2 fuel">
<density units="macro" value="1.1" />
<macroscopic name="UO2" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-5 -5 -5 5 5 5</parameters>
</space>
</source>
<energy_mode>multi-group</energy_mode>
</settings>
<model>
<materials>
<cross_sections>mgxs.h5</cross_sections>
<material id="1" name="UO2 fuel">
<density units="macro" value="1.1" />
<macroscopic name="UO2" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="cell 1" region="4 -5 6 -7" universe="0" />
<surface boundary="reflective" coeffs="-5.0" id="4" name="left" type="x-plane" />
<surface boundary="vacuum" coeffs="5.0" id="5" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-5.0" id="6" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="5.0" id="7" name="top" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-5 -5 -5 5 5 5</parameters>
</space>
</source>
<energy_mode>multi-group</energy_mode>
</settings>
</model>

View file

@ -61,7 +61,8 @@ def build_mgxs_library(convert):
class MGXSTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
# Instantiate some Macroscopic Data
uo2_data = openmc.Macroscopic('UO2')
@ -73,7 +74,7 @@ class MGXSTestHarness(PyAPITestHarness):
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([mat])
materials_file.cross_sections = "./mgxs.h5"
materials_file.export_to_xml()
self._model.materials = materials_file
# Instantiate ZCylinder surfaces
left = openmc.XPlane(surface_id=4, x0=-5., name='left')
@ -102,8 +103,7 @@ class MGXSTestHarness(PyAPITestHarness):
root.add_cells([fuel])
# Instantiate a Geometry, register the root Universe, and export to XML
geometry = openmc.Geometry(root)
geometry.export_to_xml()
self._model.geometry = openmc.Geometry(root)
settings_file = openmc.Settings()
settings_file.energy_mode = "multi-group"
@ -116,7 +116,7 @@ class MGXSTestHarness(PyAPITestHarness):
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:])
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.export_to_xml()
self._model.settings = settings_file
def _run_openmc(self):
# Run multiple conversions to compare results
@ -194,5 +194,5 @@ class MGXSTestHarness(PyAPITestHarness):
def test_mg_convert():
harness = MGXSTestHarness('statepoint.10.h5')
harness = MGXSTestHarness('statepoint.10.h5', model=openmc.Model())
harness.main()

View file

@ -1,33 +1,33 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="2" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="mat_1">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
<model>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="mat_1">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="2" type="x-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
</model>

View file

@ -1,34 +1,34 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="2" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="mat_1">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<max_order>1</max_order>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
<model>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="mat_1">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="2" type="x-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<max_order>1</max_order>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
</model>

View file

@ -1,34 +1,34 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="2" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="mat_1">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<survival_biasing>true</survival_biasing>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
<model>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="mat_1">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="2" type="x-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<survival_biasing>true</survival_biasing>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
</model>

View file

@ -1,165 +1,164 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="2" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="mat_1">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>0.0 0.0 0.0</lower_left>
<upper_right>929.45 1000 1000</upper_right>
</mesh>
<filter id="5" type="mesh">
<bins>1</bins>
</filter>
<filter id="6" type="material">
<bins>1</bins>
</filter>
<filter id="1" type="energy">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="2" type="energyout">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="3" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="4" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<tally id="1">
<filters>5</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="2">
<filters>5</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>6 1</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="4">
<filters>6 1</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="5">
<filters>6 1</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="6">
<filters>6 1 2</filters>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="7">
<filters>6 3</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>6 3</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="9">
<filters>6 3</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10">
<filters>6 3 4</filters>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="11">
<filters>5</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>analog</estimator>
</tally>
<tally id="12">
<filters>5</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>6 1</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="14">
<filters>6 1</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>collision</estimator>
</tally>
<tally id="15">
<filters>6 1</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="16">
<filters>6 1 2</filters>
<nuclides>mat_1</nuclides>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="17">
<filters>6 3</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>6 3</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>collision</estimator>
</tally>
<tally id="19">
<filters>6 3</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="20">
<filters>6 3 4</filters>
<nuclides>mat_1</nuclides>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
</tallies>
<model>
<materials>
<cross_sections>2g.h5</cross_sections>
<material id="1" name="mat_1">
<density units="macro" value="1.0" />
<macroscopic name="mat_1" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="1 -2" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="929.45" id="2" type="x-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>0.0 -1000.0 -1000.0 929.45 1000.0 1000.0</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<tabular_legendre>
<enable>false</enable>
</tabular_legendre>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>0.0 0.0 0.0</lower_left>
<upper_right>929.45 1000 1000</upper_right>
</mesh>
<filter id="5" type="mesh">
<bins>1</bins>
</filter>
<filter id="6" type="material">
<bins>1</bins>
</filter>
<filter id="1" type="energy">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="2" type="energyout">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="3" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="4" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<tally id="1">
<filters>5</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="2">
<filters>5</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>6 1</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="4">
<filters>6 1</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="5">
<filters>6 1</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="6">
<filters>6 1 2</filters>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="7">
<filters>6 3</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>6 3</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="9">
<filters>6 3</filters>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10">
<filters>6 3 4</filters>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="11">
<filters>5</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>analog</estimator>
</tally>
<tally id="12">
<filters>5</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>6 1</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="14">
<filters>6 1</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>collision</estimator>
</tally>
<tally id="15">
<filters>6 1</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="16">
<filters>6 1 2</filters>
<nuclides>mat_1</nuclides>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="17">
<filters>6 3</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>6 3</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>collision</estimator>
</tally>
<tally id="19">
<filters>6 3</filters>
<nuclides>mat_1</nuclides>
<scores>total absorption fission nu-fission inverse-velocity prompt-nu-fission delayed-nu-fission kappa-fission events decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="20">
<filters>6 3 4</filters>
<nuclides>mat_1</nuclides>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
</tallies>
</model>

View file

@ -1,251 +1,250 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="7" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="11" type="legendre">
<order>3</order>
</filter>
<filter id="15" type="material">
<bins>2</bins>
</filter>
<filter id="29" type="material">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="4">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="6">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="7">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 2 7 11</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="9">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="11">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="12">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="14">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="15">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>15 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>15 2 7 11</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>15 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="20">
<filters>15 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="21">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="23">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="24">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="25">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="26">
<filters>29 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>29 2 7 11</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>29 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>29 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="7" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="11" type="legendre">
<order>3</order>
</filter>
<filter id="15" type="material">
<bins>2</bins>
</filter>
<filter id="29" type="material">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="4">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="6">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="7">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 2 7 11</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="9">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="11">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="12">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="14">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="15">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>15 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>15 2 7 11</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>15 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="20">
<filters>15 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="21">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="23">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="24">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="25">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="26">
<filters>29 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>29 2 7 11</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>29 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>29 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
</tallies>
</model>

View file

@ -48,15 +48,12 @@ class MGXSTestHarness(PyAPITestHarness):
# Modify materials and settings so we can run in MG mode
self._model.materials.cross_sections = './mgxs.h5'
self._model.settings.energy_mode = 'multi-group'
# Dont need tallies so clear them from the model
self._model.tallies = openmc.Tallies()
# Write modified input files
self._model.settings.export_to_xml()
self._model.geometry.export_to_xml()
self._model.materials.export_to_xml()
self._model.export_to_model_xml()
self._model.mgxs_file.export_to_hdf5()
# Dont need tallies.xml, so remove the file
if os.path.exists('tallies.xml'):
os.remove('tallies.xml')
# Enforce closing statepoint and summary files so HDF5
# does not throw an error during the next OpenMC execution

View file

@ -1,251 +1,250 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="7" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="11" type="legendre">
<order>3</order>
</filter>
<filter id="15" type="material">
<bins>2</bins>
</filter>
<filter id="29" type="material">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2">
<filters>1 2</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="4">
<filters>1 2</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="6">
<filters>1 2 7</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="7">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 2 7 11</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="9">
<filters>1 2 7</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 2 7</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="11">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="12">
<filters>15 2</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="14">
<filters>15 2</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="15">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>15 2 7</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>15 2 7 11</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>15 2 7</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="20">
<filters>15 2 7</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="21">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>29 2</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="23">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="24">
<filters>29 2</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="25">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="26">
<filters>29 2 7</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>29 2 7 11</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>29 2 7</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>29 2 7</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="7" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="11" type="legendre">
<order>3</order>
</filter>
<filter id="15" type="material">
<bins>2</bins>
</filter>
<filter id="29" type="material">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2">
<filters>1 2</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="4">
<filters>1 2</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="6">
<filters>1 2 7</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="7">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 2 7 11</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="9">
<filters>1 2 7</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 2 7</filters>
<nuclides>U234 U235 U238 O16</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="11">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="12">
<filters>15 2</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="14">
<filters>15 2</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="15">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>15 2 7</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>15 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>15 2 7 11</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>15 2 7</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="20">
<filters>15 2 7</filters>
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="21">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>29 2</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="23">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="24">
<filters>29 2</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="25">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="26">
<filters>29 2 7</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>29 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>29 2 7 11</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>29 2 7</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>29 2 7</filters>
<nuclides>H1 O16 B10 B11</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
</tallies>
</model>

View file

@ -48,15 +48,12 @@ class MGXSTestHarness(PyAPITestHarness):
# Modify materials and settings so we can run in MG mode
self._model.materials.cross_sections = './mgxs.h5'
self._model.settings.energy_mode = 'multi-group'
# Dont need tallies so clear them from the model
self._model.tallies = openmc.Tallies()
# Write modified input files
self._model.settings.export_to_xml()
self._model.geometry.export_to_xml()
self._model.materials.export_to_xml()
self._model.export_to_model_xml()
self._model.mgxs_file.export_to_hdf5()
# Dont need tallies.xml, so remove the file
if os.path.exists('tallies.xml'):
os.remove('tallies.xml')
# Enforce closing statepoint and summary files so HDF5
# does not throw an error during the next OpenMC execution

File diff suppressed because it is too large Load diff

View file

@ -1,344 +1,343 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="3" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="4" type="legendre">
<order>1</order>
</filter>
<filter id="12" type="legendre">
<order>0</order>
</filter>
<filter id="19" type="material">
<bins>2</bins>
</filter>
<filter id="37" type="material">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="2">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="4">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="6">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="7">
<filters>1 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="9">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="11">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="12">
<filters>1 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="13">
<filters>1 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="14">
<filters>1 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="15">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>19 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>19 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="20">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="21">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>19 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="23">
<filters>19 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="24">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="25">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="26">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="27">
<filters>19 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>19 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>19 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="31">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="32">
<filters>37 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="33">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="34">
<filters>37 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="35">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="36">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="37">
<filters>37 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="38">
<filters>37 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="39">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="40">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="41">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="42">
<filters>37 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="43">
<filters>37 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="44">
<filters>37 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="45">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="3" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="4" type="legendre">
<order>1</order>
</filter>
<filter id="12" type="legendre">
<order>0</order>
</filter>
<filter id="19" type="material">
<bins>2</bins>
</filter>
<filter id="37" type="material">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="2">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="4">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="6">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="7">
<filters>1 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="9">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="11">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="12">
<filters>1 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="13">
<filters>1 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="14">
<filters>1 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="15">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>19 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>19 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="20">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="21">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>19 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="23">
<filters>19 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="24">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="25">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="26">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="27">
<filters>19 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>19 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>19 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>19 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="31">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="32">
<filters>37 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="33">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="34">
<filters>37 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="35">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="36">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="37">
<filters>37 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="38">
<filters>37 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="39">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="40">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="41">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="42">
<filters>37 2 3 12</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="43">
<filters>37 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="44">
<filters>37 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="45">
<filters>37 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
</tallies>
</model>

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@ -1,269 +1,268 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="3" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="4" type="mu">
<bins>-1.0 -0.8181818181818181 -0.6363636363636364 -0.4545454545454546 -0.2727272727272727 -0.09090909090909083 0.09090909090909083 0.2727272727272727 0.4545454545454546 0.6363636363636365 0.8181818181818183 1.0</bins>
</filter>
<filter id="17" type="material">
<bins>2</bins>
</filter>
<filter id="33" type="material">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="2">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="4">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="6">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="7">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="9">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="11">
<filters>1 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="12">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="13">
<filters>17 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="14">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
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@ -1,55 +1,54 @@
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View file

@ -1,45 +1,44 @@
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View file

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View file

@ -1,34 +1,34 @@
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View file

@ -1,24 +1,24 @@
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View file

@ -1,68 +1,67 @@
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View file

@ -1,49 +1,48 @@
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View file

@ -1,45 +1,44 @@
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</cutoff>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="particle">
<bins>photon</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux (n,gamma)</scores>
</tally>
</tallies>
<model>
<materials>
<material id="1">
<density units="g/cm3" value="0.998207" />
<nuclide ao="0.11187657362844" name="H1" />
<nuclide ao="1.7426371559999997e-05" name="H2" />
<nuclide ao="0.8877694078259999" name="O16" />
<nuclide ao="0.000336592174" name="O17" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="reflective" coeffs="0.0 0.0 0.0 1000000000.0" id="1" type="sphere" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>10000</particles>
<batches>1</batches>
<source particle="photon" strength="1.0">
<space type="point">
<parameters>0 0 0</parameters>
</space>
<angle type="isotropic" />
<energy type="discrete">
<parameters>10000000.0 1.0</parameters>
</energy>
</source>
<electron_treatment>ttb</electron_treatment>
<photon_transport>true</photon_transport>
<cutoff>
<energy_photon>1000.0</energy_photon>
</cutoff>
</settings>
<tallies>
<filter id="1" type="particle">
<bins>photon</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux (n,gamma)</scores>
</tally>
</tallies>
</model>

View file

@ -7,20 +7,19 @@ from tests.testing_harness import PyAPITestHarness
class SourceTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
mat = openmc.Material()
mat.set_density('g/cm3', 0.998207)
mat.add_element('H', 0.111894)
mat.add_element('O', 0.888106)
materials = openmc.Materials([mat])
materials.export_to_xml()
self._model.materials = openmc.Materials([mat])
sphere = openmc.Sphere(r=1.0e9, boundary_type='reflective')
inside_sphere = openmc.Cell()
inside_sphere.region = -sphere
inside_sphere.fill = mat
geometry = openmc.Geometry([inside_sphere])
geometry.export_to_xml()
self._model.geometry = openmc.Geometry([inside_sphere])
source = openmc.Source()
source.space = openmc.stats.Point((0, 0, 0))
@ -36,16 +35,16 @@ class SourceTestHarness(PyAPITestHarness):
settings.cutoff = {'energy_photon' : 1000.0}
settings.run_mode = 'fixed source'
settings.source = source
settings.export_to_xml()
self._model.settings = settings
particle_filter = openmc.ParticleFilter('photon')
tally = openmc.Tally()
tally.filters = [particle_filter]
tally.scores = ['flux', '(n,gamma)']
tallies = openmc.Tallies([tally])
tallies.export_to_xml()
self._model.tallies = tallies
def test_photon_source():
harness = SourceTestHarness('statepoint.1.h5')
harness = SourceTestHarness('statepoint.1.h5', model=openmc.Model())
harness.main()

View file

@ -1,34 +1,34 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-9" universe="0" />
<surface boundary="reflective" coeffs="100" id="9" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="U238" />
<nuclide ao="0.02" name="U235" />
<nuclide ao="0.02" name="Pu239" />
<nuclide ao="20.0" name="H1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
<resonance_scattering>
<enable>true</enable>
<method>rvs</method>
<energy_min>1.0</energy_min>
<energy_max>210.0</energy_max>
<nuclides>U238 U235 Pu239</nuclides>
</resonance_scattering>
</settings>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="U238" />
<nuclide ao="0.02" name="U235" />
<nuclide ao="0.02" name="Pu239" />
<nuclide ao="20.0" name="H1" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="0" />
<surface boundary="reflective" coeffs="100" id="1" type="x-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
<resonance_scattering>
<enable>true</enable>
<method>rvs</method>
<energy_min>1.0</energy_min>
<energy_max>210.0</energy_max>
<nuclides>U238 U235 Pu239</nuclides>
</resonance_scattering>
</settings>
</model>

View file

@ -4,7 +4,8 @@ from tests.testing_harness import PyAPITestHarness
class ResonanceScatteringTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
# Materials
mat = openmc.Material(material_id=1)
mat.set_density('g/cc', 1.0)
@ -13,15 +14,13 @@ class ResonanceScatteringTestHarness(PyAPITestHarness):
mat.add_nuclide('Pu239', 0.02)
mat.add_nuclide('H1', 20.0)
mats_file = openmc.Materials([mat])
mats_file.export_to_xml()
self._model.materials = openmc.Materials([mat])
# Geometry
dumb_surface = openmc.XPlane(100, boundary_type='reflective')
c1 = openmc.Cell(cell_id=1, fill=mat, region=-dumb_surface)
root_univ = openmc.Universe(universe_id=0, cells=[c1])
geometry = openmc.Geometry(root_univ)
geometry.export_to_xml()
self._model.geometry = openmc.Geometry(root_univ)
# Resonance elastic scattering settings
res_scat_settings = {
@ -39,9 +38,10 @@ class ResonanceScatteringTestHarness(PyAPITestHarness):
settings.source = openmc.source.Source(
space=openmc.stats.Box([-4, -4, -4], [4, 4, 4]))
settings.resonance_scattering = res_scat_settings
settings.export_to_xml()
self._model.settings = settings
def test_resonance_scattering():
harness = ResonanceScatteringTestHarness('statepoint.10.h5')
harness = ResonanceScatteringTestHarness('statepoint.10.h5',
model=openmc.Model())
harness.main()

View file

@ -1,60 +1,60 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="1 -2" universe="1" />
<cell id="2" material="2" region="2 -3" universe="1" />
<cell id="3" material="3" region="3 -4" universe="1" />
<cell id="4" material="4" region="4 -5" universe="1" />
<surface boundary="vacuum" coeffs="-10" id="1" type="x-plane" />
<surface coeffs="-5" id="2" type="x-plane" />
<surface coeffs="0" id="3" type="x-plane" />
<surface coeffs="5" id="4" type="x-plane" />
<surface boundary="vacuum" coeffs="10" id="5" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="H1" />
<sab fraction="0.5" name="c_H_in_H2O" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
<material depletable="true" id="3">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="Be9" />
<nuclide ao="1.0" name="O16" />
<sab name="c_Be_in_BeO" />
<sab name="c_O_in_BeO" />
</material>
<material depletable="true" id="4">
<density units="g/cm3" value="5.90168" />
<nuclide ao="0.3" name="H1" />
<nuclide ao="0.15" name="Zr90" />
<nuclide ao="0.1" name="Zr91" />
<nuclide ao="0.1" name="Zr92" />
<nuclide ao="0.05" name="Zr94" />
<nuclide ao="0.05" name="Zr96" />
<nuclide ao="0.1" name="U235" />
<nuclide ao="0.15" name="U238" />
<sab name="c_Zr_in_ZrH" />
<sab name="c_H_in_ZrH" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>400</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="H1" />
<sab fraction="0.5" name="c_H_in_H2O" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
<material depletable="true" id="3">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="Be9" />
<nuclide ao="1.0" name="O16" />
<sab name="c_Be_in_BeO" />
<sab name="c_O_in_BeO" />
</material>
<material depletable="true" id="4">
<density units="g/cm3" value="5.90168" />
<nuclide ao="0.3" name="H1" />
<nuclide ao="0.15" name="Zr90" />
<nuclide ao="0.1" name="Zr91" />
<nuclide ao="0.1" name="Zr92" />
<nuclide ao="0.05" name="Zr94" />
<nuclide ao="0.05" name="Zr96" />
<nuclide ao="0.1" name="U235" />
<nuclide ao="0.15" name="U238" />
<sab name="c_Zr_in_ZrH" />
<sab name="c_H_in_ZrH" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="1 -2" universe="1" />
<cell id="2" material="2" region="2 -3" universe="1" />
<cell id="3" material="3" region="3 -4" universe="1" />
<cell id="4" material="4" region="4 -5" universe="1" />
<surface boundary="vacuum" coeffs="-10" id="1" type="x-plane" />
<surface coeffs="-5" id="2" type="x-plane" />
<surface coeffs="0" id="3" type="x-plane" />
<surface coeffs="5" id="4" type="x-plane" />
<surface boundary="vacuum" coeffs="10" id="5" type="x-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>400</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>
</model>

View file

@ -1,55 +1,54 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="1 -2 3 -4 10 -9" universe="1" />
<cell id="2" material="2" region="~(1 -2 3 -4) (5 -6 7 -8) 10 -9" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface boundary="reflective" coeffs="-10.0" id="5" name="minimum x" type="x-plane" />
<surface boundary="reflective" coeffs="10.0" id="6" name="maximum x" type="x-plane" />
<surface boundary="reflective" coeffs="-10.0" id="7" name="minimum y" type="y-plane" />
<surface boundary="reflective" coeffs="10.0" id="8" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="9" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="10" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2">
<density units="g/cm3" value="1.0" />
<nuclide ao="1.0" name="Zr90" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>3 3 3</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<filter id="1" type="meshsurface">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.253 20000000.0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>current</scores>
</tally>
<tally id="2">
<filters>1 2</filters>
<scores>current</scores>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2">
<density units="g/cm3" value="1.0" />
<nuclide ao="1.0" name="Zr90" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="1 -2 3 -4 10 -9" universe="1" />
<cell id="2" material="2" region="~(1 -2 3 -4) (5 -6 7 -8) 10 -9" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface boundary="reflective" coeffs="-10.0" id="5" name="minimum x" type="x-plane" />
<surface boundary="reflective" coeffs="10.0" id="6" name="maximum x" type="x-plane" />
<surface boundary="reflective" coeffs="-10.0" id="7" name="minimum y" type="y-plane" />
<surface boundary="reflective" coeffs="10.0" id="8" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="9" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="10" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
</settings>
<tallies>
<mesh id="1">
<dimension>3 3 3</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<filter id="1" type="meshsurface">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.253 20000000.0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>current</scores>
</tally>
<tally id="2">
<filters>1 2</filters>
<scores>current</scores>
</tally>
</tallies>
</model>

View file

@ -1,150 +1,150 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="0" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 10.0" id="1" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" temperature="294">
<density units="g/cm3" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="0.3">
<space type="cartesian">
<x parameters="-3.0 3.0" type="uniform" />
<y type="discrete">
<parameters>-4.0 -1.0 3.0 0.2 0.3 0.5</parameters>
</y>
<z interpolation="linear-linear" type="tabular">
<parameters>-2.0 0.0 2.0 0.2 0.3 0.2</parameters>
</z>
</space>
<angle reference_uvw="0.0 0.0 1.0" type="mu-phi">
<mu type="discrete">
<parameters>-1.0 0.0 1.0 0.5 0.25 0.25</parameters>
</mu>
<phi parameters="0.0 6.28318530718" type="uniform" />
</angle>
<energy parameters="1289500.0" type="maxwell" />
</source>
<source strength="0.1">
<space type="box">
<parameters>-4.0 -4.0 -4.0 4.0 4.0 4.0</parameters>
</space>
<angle reference_uvw="0.0 1.0 0.0" type="monodirectional" />
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<source strength="0.1">
<space type="point">
<parameters>1.2 -2.3 0.781</parameters>
</space>
<angle type="isotropic" />
<energy interpolation="histogram" type="tabular">
<parameters>1.0 1.3894954943731377 1.93069772888325 2.6826957952797255 3.72759372031494 5.17947467923121 7.196856730011519 10.0 13.894954943731374 19.306977288832496 26.826957952797247 37.2759372031494 51.7947467923121 71.96856730011518 100.0 138.94954943731375 193.06977288832496 268.26957952797244 372.7593720314938 517.9474679231207 719.6856730011514 1000.0 1389.4954943731375 1930.6977288832495 2682.6957952797247 3727.593720314938 5179.474679231207 7196.856730011514 10000.0 13894.95494373136 19306.977288832495 26826.95795279722 37275.93720314938 51794.74679231213 71968.56730011514 100000.0 138949.5494373136 193069.77288832495 268269.5795279722 372759.3720314938 517947.4679231202 719685.6730011514 1000000.0 1389495.494373136 1930697.7288832497 2682695.7952797217 3727593.720314938 5179474.679231202 7196856.730011513 10000000.0 0.0 2.9086439299358713e-08 5.80533561806147e-08 8.67817193689187e-08 1.1515347785771536e-07 1.4305204600565115e-07 1.7036278261198208e-07 1.9697346200185813e-07 2.227747351856934e-07 2.4766057919761985e-07 2.715287327665956e-07 2.9428111652990295e-07 3.1582423606228735e-07 3.360695660646056e-07 3.549339141332686e-07 3.723397626156721e-07 3.882155871468592e-07 4.024961505584776e-07 4.151227709522976e-07 4.260435628367196e-07 4.3521365033538783e-07 4.4259535159179273e-07 4.4815833361210174e-07 4.5187973690993757e-07 4.5374426944091084e-07 4.5374426944091084e-07 4.5187973690993757e-07 4.4815833361210174e-07 4.4259535159179273e-07 4.352136503353879e-07 4.2604356283671966e-07 4.1512277095229767e-07 4.0249615055847764e-07 3.8821558714685926e-07 3.723397626156722e-07 3.5493391413326864e-07 3.360695660646057e-07 3.158242360622874e-07 2.942811165299031e-07 2.715287327665957e-07 2.4766057919762e-07 2.2277473518569352e-07 1.9697346200185819e-07 1.7036278261198226e-07 1.4305204600565126e-07 1.1515347785771556e-07 8.678171936891881e-08 5.805335618061493e-08 2.9086439299358858e-08 5.559621115282002e-23</parameters>
</energy>
</source>
<source strength="0.1">
<space origin="1.0 1.0 0.0" type="spherical">
<r parameters="2.0 3.0" type="uniform" />
<cos_theta type="discrete">
<parameters>0.7071067811865476 0.0 -0.7071067811865475 0.3 0.4 0.3</parameters>
</cos_theta>
<phi parameters="0.0 6.283185307179586" type="uniform" />
</space>
<angle type="isotropic" />
<energy interpolation="histogram" type="tabular">
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<parameters>1.0 1.3894954943731377 1.93069772888325 2.6826957952797255 3.72759372031494 5.17947467923121 7.196856730011519 10.0 13.894954943731374 19.306977288832496 26.826957952797247 37.2759372031494 51.7947467923121 71.96856730011518 100.0 138.94954943731375 193.06977288832496 268.26957952797244 372.7593720314938 517.9474679231207 719.6856730011514 1000.0 1389.4954943731375 1930.6977288832495 2682.6957952797247 3727.593720314938 5179.474679231207 7196.856730011514 10000.0 13894.95494373136 19306.977288832495 26826.95795279722 37275.93720314938 51794.74679231213 71968.56730011514 100000.0 138949.5494373136 193069.77288832495 268269.5795279722 372759.3720314938 517947.4679231202 719685.6730011514 1000000.0 1389495.494373136 1930697.7288832497 2682695.7952797217 3727593.720314938 5179474.679231202 7196856.730011513 10000000.0 0.0 2.9086439299358713e-08 5.80533561806147e-08 8.67817193689187e-08 1.1515347785771536e-07 1.4305204600565115e-07 1.7036278261198208e-07 1.9697346200185813e-07 2.227747351856934e-07 2.4766057919761985e-07 2.715287327665956e-07 2.9428111652990295e-07 3.1582423606228735e-07 3.360695660646056e-07 3.549339141332686e-07 3.723397626156721e-07 3.882155871468592e-07 4.024961505584776e-07 4.151227709522976e-07 4.260435628367196e-07 4.3521365033538783e-07 4.4259535159179273e-07 4.4815833361210174e-07 4.5187973690993757e-07 4.5374426944091084e-07 4.5374426944091084e-07 4.5187973690993757e-07 4.4815833361210174e-07 4.4259535159179273e-07 4.352136503353879e-07 4.2604356283671966e-07 4.1512277095229767e-07 4.0249615055847764e-07 3.8821558714685926e-07 3.723397626156722e-07 3.5493391413326864e-07 3.360695660646057e-07 3.158242360622874e-07 2.942811165299031e-07 2.715287327665957e-07 2.4766057919762e-07 2.2277473518569352e-07 1.9697346200185819e-07 1.7036278261198226e-07 1.4305204600565126e-07 1.1515347785771556e-07 8.678171936891881e-08 5.805335618061493e-08 2.9086439299358858e-08 5.559621115282002e-23</parameters>
</energy>
</source>
<source strength="0.1">
<space origin="1.0 1.0 0.0" type="cylindrical">
<r parameters="2.0 3.0" type="uniform" />
<phi parameters="0.0 6.283185307179586" type="uniform" />
<z interpolation="linear-linear" type="tabular">
<parameters>-2.0 0.0 2.0 0.2 0.3 0.2</parameters>
</z>
</space>
<angle type="isotropic" />
<energy interpolation="histogram" type="tabular">
<parameters>1.0 1.3894954943731377 1.93069772888325 2.6826957952797255 3.72759372031494 5.17947467923121 7.196856730011519 10.0 13.894954943731374 19.306977288832496 26.826957952797247 37.2759372031494 51.7947467923121 71.96856730011518 100.0 138.94954943731375 193.06977288832496 268.26957952797244 372.7593720314938 517.9474679231207 719.6856730011514 1000.0 1389.4954943731375 1930.6977288832495 2682.6957952797247 3727.593720314938 5179.474679231207 7196.856730011514 10000.0 13894.95494373136 19306.977288832495 26826.95795279722 37275.93720314938 51794.74679231213 71968.56730011514 100000.0 138949.5494373136 193069.77288832495 268269.5795279722 372759.3720314938 517947.4679231202 719685.6730011514 1000000.0 1389495.494373136 1930697.7288832497 2682695.7952797217 3727593.720314938 5179474.679231202 7196856.730011513 10000000.0 0.0 2.9086439299358713e-08 5.80533561806147e-08 8.67817193689187e-08 1.1515347785771536e-07 1.4305204600565115e-07 1.7036278261198208e-07 1.9697346200185813e-07 2.227747351856934e-07 2.4766057919761985e-07 2.715287327665956e-07 2.9428111652990295e-07 3.1582423606228735e-07 3.360695660646056e-07 3.549339141332686e-07 3.723397626156721e-07 3.882155871468592e-07 4.024961505584776e-07 4.151227709522976e-07 4.260435628367196e-07 4.3521365033538783e-07 4.4259535159179273e-07 4.4815833361210174e-07 4.5187973690993757e-07 4.5374426944091084e-07 4.5374426944091084e-07 4.5187973690993757e-07 4.4815833361210174e-07 4.4259535159179273e-07 4.352136503353879e-07 4.2604356283671966e-07 4.1512277095229767e-07 4.0249615055847764e-07 3.8821558714685926e-07 3.723397626156722e-07 3.5493391413326864e-07 3.360695660646057e-07 3.158242360622874e-07 2.942811165299031e-07 2.715287327665957e-07 2.4766057919762e-07 2.2277473518569352e-07 1.9697346200185819e-07 1.7036278261198226e-07 1.4305204600565126e-07 1.1515347785771556e-07 8.678171936891881e-08 5.805335618061493e-08 2.9086439299358858e-08 5.559621115282002e-23</parameters>
</energy>
</source>
<source strength="0.1">
<space origin="1.0 1.0 0.0" type="cylindrical">
<r parameters="2.0 3.0" type="uniform" />
<phi parameters="0.0 6.283185307179586" type="uniform" />
<z interpolation="linear-linear" type="tabular">
<parameters>-2.0 0.0 2.0 0.2 0.3 0.2</parameters>
</z>
</space>
<angle type="isotropic" />
<energy type="mixture">
<pair probability="1">
<dist parameters="1289500.0" type="maxwell" />
</pair>
<pair probability="2">
<dist parameters="988000.0 2.249e-06" type="watt" />
</pair>
<pair probability="3">
<dist interpolation="histogram" type="tabular">
<parameters>1.0 1.3894954943731377 1.93069772888325 2.6826957952797255 3.72759372031494 5.17947467923121 7.196856730011519 10.0 13.894954943731374 19.306977288832496 26.826957952797247 37.2759372031494 51.7947467923121 71.96856730011518 100.0 138.94954943731375 193.06977288832496 268.26957952797244 372.7593720314938 517.9474679231207 719.6856730011514 1000.0 1389.4954943731375 1930.6977288832495 2682.6957952797247 3727.593720314938 5179.474679231207 7196.856730011514 10000.0 13894.95494373136 19306.977288832495 26826.95795279722 37275.93720314938 51794.74679231213 71968.56730011514 100000.0 138949.5494373136 193069.77288832495 268269.5795279722 372759.3720314938 517947.4679231202 719685.6730011514 1000000.0 1389495.494373136 1930697.7288832497 2682695.7952797217 3727593.720314938 5179474.679231202 7196856.730011513 10000000.0 0.0 2.9086439299358713e-08 5.80533561806147e-08 8.67817193689187e-08 1.1515347785771536e-07 1.4305204600565115e-07 1.7036278261198208e-07 1.9697346200185813e-07 2.227747351856934e-07 2.4766057919761985e-07 2.715287327665956e-07 2.9428111652990295e-07 3.1582423606228735e-07 3.360695660646056e-07 3.549339141332686e-07 3.723397626156721e-07 3.882155871468592e-07 4.024961505584776e-07 4.151227709522976e-07 4.260435628367196e-07 4.3521365033538783e-07 4.4259535159179273e-07 4.4815833361210174e-07 4.5187973690993757e-07 4.5374426944091084e-07 4.5374426944091084e-07 4.5187973690993757e-07 4.4815833361210174e-07 4.4259535159179273e-07 4.352136503353879e-07 4.2604356283671966e-07 4.1512277095229767e-07 4.0249615055847764e-07 3.8821558714685926e-07 3.723397626156722e-07 3.5493391413326864e-07 3.360695660646057e-07 3.158242360622874e-07 2.942811165299031e-07 2.715287327665957e-07 2.4766057919762e-07 2.2277473518569352e-07 1.9697346200185819e-07 1.7036278261198226e-07 1.4305204600565126e-07 1.1515347785771556e-07 8.678171936891881e-08 5.805335618061493e-08 2.9086439299358858e-08 5.559621115282002e-23</parameters>
</dist>
</pair>
</energy>
</source>
<source strength="0.1">
<space origin="1.0 1.0 0.0" type="spherical">
<r parameters="2.0 3.0 2.0" type="powerlaw" />
<cos_theta type="discrete">
<parameters>0.7071067811865476 0.0 -0.7071067811865475 0.3 0.4 0.3</parameters>
</cos_theta>
<phi parameters="0.0 6.283185307179586" type="uniform" />
</space>
<angle type="isotropic" />
<energy type="mixture">
<pair probability="1">
<dist parameters="1289500.0" type="maxwell" />
</pair>
<pair probability="2">
<dist parameters="988000.0 2.249e-06" type="watt" />
</pair>
<pair probability="3">
<dist interpolation="histogram" type="tabular">
<parameters>1.0 1.3894954943731377 1.93069772888325 2.6826957952797255 3.72759372031494 5.17947467923121 7.196856730011519 10.0 13.894954943731374 19.306977288832496 26.826957952797247 37.2759372031494 51.7947467923121 71.96856730011518 100.0 138.94954943731375 193.06977288832496 268.26957952797244 372.7593720314938 517.9474679231207 719.6856730011514 1000.0 1389.4954943731375 1930.6977288832495 2682.6957952797247 3727.593720314938 5179.474679231207 7196.856730011514 10000.0 13894.95494373136 19306.977288832495 26826.95795279722 37275.93720314938 51794.74679231213 71968.56730011514 100000.0 138949.5494373136 193069.77288832495 268269.5795279722 372759.3720314938 517947.4679231202 719685.6730011514 1000000.0 1389495.494373136 1930697.7288832497 2682695.7952797217 3727593.720314938 5179474.679231202 7196856.730011513 10000000.0 0.0 2.9086439299358713e-08 5.80533561806147e-08 8.67817193689187e-08 1.1515347785771536e-07 1.4305204600565115e-07 1.7036278261198208e-07 1.9697346200185813e-07 2.227747351856934e-07 2.4766057919761985e-07 2.715287327665956e-07 2.9428111652990295e-07 3.1582423606228735e-07 3.360695660646056e-07 3.549339141332686e-07 3.723397626156721e-07 3.882155871468592e-07 4.024961505584776e-07 4.151227709522976e-07 4.260435628367196e-07 4.3521365033538783e-07 4.4259535159179273e-07 4.4815833361210174e-07 4.5187973690993757e-07 4.5374426944091084e-07 4.5374426944091084e-07 4.5187973690993757e-07 4.4815833361210174e-07 4.4259535159179273e-07 4.352136503353879e-07 4.2604356283671966e-07 4.1512277095229767e-07 4.0249615055847764e-07 3.8821558714685926e-07 3.723397626156722e-07 3.5493391413326864e-07 3.360695660646057e-07 3.158242360622874e-07 2.942811165299031e-07 2.715287327665957e-07 2.4766057919762e-07 2.2277473518569352e-07 1.9697346200185819e-07 1.7036278261198226e-07 1.4305204600565126e-07 1.1515347785771556e-07 8.678171936891881e-08 5.805335618061493e-08 2.9086439299358858e-08 5.559621115282002e-23</parameters>
</dist>
</pair>
</energy>
<time parameters="2 5" type="uniform" />
</source>
<source strength="0.1">
<space origin="1.0 1.0 0.0" type="cylindrical">
<r parameters="2.0 3.0 1.0" type="powerlaw" />
<phi parameters="0.0 6.283185307179586" type="uniform" />
<z interpolation="linear-linear" type="tabular">
<parameters>-2.0 0.0 2.0 0.2 0.3 0.2</parameters>
</z>
</space>
<angle type="isotropic" />
<energy type="mixture">
<pair probability="1">
<dist parameters="1289500.0" type="maxwell" />
</pair>
<pair probability="2">
<dist parameters="988000.0 2.249e-06" type="watt" />
</pair>
<pair probability="3">
<dist interpolation="histogram" type="tabular">
<parameters>1.0 1.3894954943731377 1.93069772888325 2.6826957952797255 3.72759372031494 5.17947467923121 7.196856730011519 10.0 13.894954943731374 19.306977288832496 26.826957952797247 37.2759372031494 51.7947467923121 71.96856730011518 100.0 138.94954943731375 193.06977288832496 268.26957952797244 372.7593720314938 517.9474679231207 719.6856730011514 1000.0 1389.4954943731375 1930.6977288832495 2682.6957952797247 3727.593720314938 5179.474679231207 7196.856730011514 10000.0 13894.95494373136 19306.977288832495 26826.95795279722 37275.93720314938 51794.74679231213 71968.56730011514 100000.0 138949.5494373136 193069.77288832495 268269.5795279722 372759.3720314938 517947.4679231202 719685.6730011514 1000000.0 1389495.494373136 1930697.7288832497 2682695.7952797217 3727593.720314938 5179474.679231202 7196856.730011513 10000000.0 0.0 2.9086439299358713e-08 5.80533561806147e-08 8.67817193689187e-08 1.1515347785771536e-07 1.4305204600565115e-07 1.7036278261198208e-07 1.9697346200185813e-07 2.227747351856934e-07 2.4766057919761985e-07 2.715287327665956e-07 2.9428111652990295e-07 3.1582423606228735e-07 3.360695660646056e-07 3.549339141332686e-07 3.723397626156721e-07 3.882155871468592e-07 4.024961505584776e-07 4.151227709522976e-07 4.260435628367196e-07 4.3521365033538783e-07 4.4259535159179273e-07 4.4815833361210174e-07 4.5187973690993757e-07 4.5374426944091084e-07 4.5374426944091084e-07 4.5187973690993757e-07 4.4815833361210174e-07 4.4259535159179273e-07 4.352136503353879e-07 4.2604356283671966e-07 4.1512277095229767e-07 4.0249615055847764e-07 3.8821558714685926e-07 3.723397626156722e-07 3.5493391413326864e-07 3.360695660646057e-07 3.158242360622874e-07 2.942811165299031e-07 2.715287327665957e-07 2.4766057919762e-07 2.2277473518569352e-07 1.9697346200185819e-07 1.7036278261198226e-07 1.4305204600565126e-07 1.1515347785771556e-07 8.678171936891881e-08 5.805335618061493e-08 2.9086439299358858e-08 5.559621115282002e-23</parameters>
</dist>
</pair>
</energy>
<time parameters="2 5" type="uniform" />
</source>
</settings>
</model>

View file

@ -7,12 +7,12 @@ from tests.testing_harness import PyAPITestHarness
class SourceTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
mat1 = openmc.Material(material_id=1, temperature=294)
mat1.set_density('g/cm3', 4.5)
mat1.add_nuclide(openmc.Nuclide('U235'), 1.0)
materials = openmc.Materials([mat1])
materials.export_to_xml()
self._model.materials = openmc.Materials([mat1])
sphere = openmc.Sphere(surface_id=1, r=10.0, boundary_type='vacuum')
inside_sphere = openmc.Cell(cell_id=1)
@ -21,9 +21,7 @@ class SourceTestHarness(PyAPITestHarness):
root = openmc.Universe(universe_id=0)
root.add_cell(inside_sphere)
geometry = openmc.Geometry()
geometry.root_universe = root
geometry.export_to_xml()
self._model.geometry = openmc.Geometry(root)
# Create an array of different sources
x_dist = openmc.stats.Uniform(-3., 3.)
@ -84,9 +82,9 @@ class SourceTestHarness(PyAPITestHarness):
settings.inactive = 5
settings.particles = 1000
settings.source = [source1, source2, source3, source4, source5, source6, source7, source8]
settings.export_to_xml()
self._model.settings = settings
def test_source():
harness = SourceTestHarness('statepoint.10.h5')
harness = SourceTestHarness('statepoint.10.h5', model=openmc.Model())
harness.main()

View file

@ -1,23 +1,23 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 100" id="1" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="natural_lead">
<density units="g/cm3" value="11.34" />
<nuclide ao="0.014" name="Pb204" />
<nuclide ao="0.241" name="Pb206" />
<nuclide ao="0.221" name="Pb207" />
<nuclide ao="0.524" name="Pb208" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>0</inactive>
<source library="build/libsource.so" strength="1.0" />
</settings>
<model>
<materials>
<material id="1" name="natural_lead">
<density units="g/cm3" value="11.34" />
<nuclide ao="0.014" name="Pb204" />
<nuclide ao="0.241" name="Pb206" />
<nuclide ao="0.221" name="Pb207" />
<nuclide ao="0.524" name="Pb208" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 100" id="1" type="sphere" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>0</inactive>
<source library="build/libsource.so" strength="1.0" />
</settings>
</model>

View file

@ -1,23 +1,23 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 100" id="1" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="natural_lead">
<density units="g/cm3" value="11.34" />
<nuclide ao="0.014" name="Pb204" />
<nuclide ao="0.241" name="Pb206" />
<nuclide ao="0.221" name="Pb207" />
<nuclide ao="0.524" name="Pb208" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>0</inactive>
<source library="build/libsource.so" parameters="1e3" strength="1.0" />
</settings>
<model>
<materials>
<material id="1" name="natural_lead">
<density units="g/cm3" value="11.34" />
<nuclide ao="0.014" name="Pb204" />
<nuclide ao="0.241" name="Pb206" />
<nuclide ao="0.221" name="Pb207" />
<nuclide ao="0.524" name="Pb208" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 100" id="1" type="sphere" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>0</inactive>
<source library="build/libsource.so" parameters="1e3" strength="1.0" />
</settings>
</model>

View file

@ -1,34 +1,33 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="void" region="-1" universe="1" />
<cell id="2" material="void" region="1 -2" universe="1" />
<cell id="3" material="void" region="2 -3" universe="1" />
<cell id="4" material="void" region="3 -4" universe="1" />
<surface coeffs="0.0 0.0 0.0 1.0" id="1" type="sphere" />
<surface coeffs="0.0 0.0 0.0 2.0" id="2" type="sphere" />
<surface coeffs="0.0 0.0 0.0 2.5" id="3" type="sphere" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 4.0" id="4" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<surf_source_read>
<path>surface_source_true.h5</path>
</surf_source_read>
<seed>1</seed>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="cell">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
<model>
<materials>
</materials>
<geometry>
<cell id="1" material="void" region="-1" universe="1" />
<cell id="2" material="void" region="1 -2" universe="1" />
<cell id="3" material="void" region="2 -3" universe="1" />
<cell id="4" material="void" region="3 -4" universe="1" />
<surface coeffs="0.0 0.0 0.0 1.0" id="1" type="sphere" />
<surface coeffs="0.0 0.0 0.0 2.0" id="2" type="sphere" />
<surface coeffs="0.0 0.0 0.0 2.5" id="3" type="sphere" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 4.0" id="4" type="sphere" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<surf_source_read>
<path>surface_source_true.h5</path>
</surf_source_read>
<seed>1</seed>
</settings>
<tallies>
<filter id="1" type="cell">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,40 +1,39 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="void" region="-1" universe="1" />
<cell id="2" material="void" region="1 -2" universe="1" />
<cell id="3" material="void" region="2 -3" universe="1" />
<cell id="4" material="void" region="3 -4" universe="1" />
<surface coeffs="0.0 0.0 0.0 1.0" id="1" type="sphere" />
<surface coeffs="0.0 0.0 0.0 2.0" id="2" type="sphere" />
<surface coeffs="0.0 0.0 0.0 2.5" id="3" type="sphere" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 4.0" id="4" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space type="point">
<parameters>0 0 0</parameters>
</space>
</source>
<surf_source_write>
<surface_ids>1</surface_ids>
<max_particles>1000</max_particles>
</surf_source_write>
<seed>1</seed>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="cell">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
<model>
<materials>
</materials>
<geometry>
<cell id="1" material="void" region="-1" universe="1" />
<cell id="2" material="void" region="1 -2" universe="1" />
<cell id="3" material="void" region="2 -3" universe="1" />
<cell id="4" material="void" region="3 -4" universe="1" />
<surface coeffs="0.0 0.0 0.0 1.0" id="1" type="sphere" />
<surface coeffs="0.0 0.0 0.0 2.0" id="2" type="sphere" />
<surface coeffs="0.0 0.0 0.0 2.5" id="3" type="sphere" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 4.0" id="4" type="sphere" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space type="point">
<parameters>0 0 0</parameters>
</space>
</source>
<surf_source_write>
<surface_ids>1</surface_ids>
<max_particles>1000</max_particles>
</surf_source_write>
<seed>1</seed>
</settings>
<tallies>
<filter id="1" type="cell">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,103 +1,102 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="13" material="13" name="fuel" region="-1" universe="9" />
<cell id="14" material="14" name="water" region="1 -3 9 -10" universe="9" />
<cell fill="9" id="15" name="root cell" region="2 -3 9 -10" universe="0" />
<surface coeffs="0 0 1" id="1" name="Fuel OR" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-2" id="2" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="2" id="3" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-2" id="9" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="2" id="10" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="13" name="UO2 fuel at 2.4% wt enrichment">
<density units="g/cc" value="10.0" />
<nuclide ao="1.0" name="U238" />
<nuclide ao="0.02" name="U235" />
<nuclide ao="2.0" name="O16" />
</material>
<material id="14" name="Borated water">
<density units="g/cm3" value="1" />
<nuclide ao="0.0001" name="B10" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.62992 -0.62992 -1 0.62992 0.62992 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="5" type="cellfrom">
<bins>13</bins>
</filter>
<filter id="6" type="cell">
<bins>14</bins>
</filter>
<filter id="1" type="energy">
<bins>0.0 4000000.0 20000000.0</bins>
</filter>
<filter id="2" type="polar">
<bins>0.0 0.7853981633974483 3.141592653589793</bins>
</filter>
<filter id="3" type="azimuthal">
<bins>0.0 0.7853981633974483 3.141592653589793</bins>
</filter>
<filter id="4" type="surface">
<bins>1</bins>
</filter>
<filter id="7" type="cellfrom">
<bins>14</bins>
</filter>
<filter id="8" type="cell">
<bins>13</bins>
</filter>
<filter id="10" type="surface">
<bins>2</bins>
</filter>
<filter id="11" type="surface">
<bins>3</bins>
</filter>
<tally id="1" name="fuel_to_water_1">
<filters>5 6 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="2" name="fuel_to_water_2">
<filters>5 4 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="3" name="water_to_fuel_1">
<filters>7 8 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="4" name="water_to_fuel_2">
<filters>7 4 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="5" name="net_cylinder">
<filters>4 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="6" name="leakage_left">
<filters>10 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="7" name="net_right">
<filters>11 1</filters>
<scores>current</scores>
</tally>
<tally id="8" name="net_right">
<filters>11 1</filters>
<scores>current</scores>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="UO2 fuel at 2.4% wt enrichment">
<density units="g/cc" value="10.0" />
<nuclide ao="1.0" name="U238" />
<nuclide ao="0.02" name="U235" />
<nuclide ao="2.0" name="O16" />
</material>
<material id="2" name="Borated water">
<density units="g/cm3" value="1" />
<nuclide ao="0.0001" name="B10" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="-1" universe="1" />
<cell id="2" material="2" name="water" region="1 -3 4 -5" universe="1" />
<cell fill="1" id="3" name="root cell" region="2 -3 4 -5" universe="0" />
<surface coeffs="0 0 1" id="1" name="Fuel OR" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-2" id="2" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="2" id="3" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-2" id="4" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="2" id="5" name="top" type="y-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.62992 -0.62992 -1 0.62992 0.62992 1</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="5" type="cellfrom">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>2</bins>
</filter>
<filter id="1" type="energy">
<bins>0.0 4000000.0 20000000.0</bins>
</filter>
<filter id="2" type="polar">
<bins>0.0 0.7853981633974483 3.141592653589793</bins>
</filter>
<filter id="3" type="azimuthal">
<bins>0.0 0.7853981633974483 3.141592653589793</bins>
</filter>
<filter id="4" type="surface">
<bins>1</bins>
</filter>
<filter id="7" type="cellfrom">
<bins>2</bins>
</filter>
<filter id="8" type="cell">
<bins>1</bins>
</filter>
<filter id="10" type="surface">
<bins>2</bins>
</filter>
<filter id="11" type="surface">
<bins>3</bins>
</filter>
<tally id="1" name="fuel_to_water_1">
<filters>5 6 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="2" name="fuel_to_water_2">
<filters>5 4 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="3" name="water_to_fuel_1">
<filters>7 8 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="4" name="water_to_fuel_2">
<filters>7 4 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="5" name="net_cylinder">
<filters>4 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="6" name="leakage_left">
<filters>10 1 2 3</filters>
<scores>current</scores>
</tally>
<tally id="7" name="net_right">
<filters>11 1</filters>
<scores>current</scores>
</tally>
<tally id="8" name="net_right">
<filters>11 1</filters>
<scores>current</scores>
</tally>
</tallies>
</model>

View file

@ -6,7 +6,8 @@ from tests.testing_harness import PyAPITestHarness
class SurfaceTallyTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
# Instantiate some Materials and register the appropriate Nuclides
uo2 = openmc.Material(name='UO2 fuel at 2.4% wt enrichment')
uo2.set_density('g/cc', 10.0)
@ -21,8 +22,7 @@ class SurfaceTallyTestHarness(PyAPITestHarness):
borated_water.add_nuclide('O16', 1.0)
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([uo2, borated_water])
materials_file.export_to_xml()
self._model.materials = openmc.Materials([uo2, borated_water])
# Instantiate ZCylinder surfaces
fuel_or = openmc.ZCylinder(surface_id=1, x0=0, y0=0, r=1,
@ -61,8 +61,7 @@ class SurfaceTallyTestHarness(PyAPITestHarness):
root_univ.add_cell(root_cell)
# Instantiate a Geometry, register the root Universe
geometry = openmc.Geometry(root_univ)
geometry.export_to_xml()
self._model.geometry = openmc.Geometry(root_univ)
# Instantiate a Settings object, set all runtime parameters
settings_file = openmc.Settings()
@ -76,7 +75,7 @@ class SurfaceTallyTestHarness(PyAPITestHarness):
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:],\
only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.export_to_xml()
self._model.settings = settings_file
# Tallies file
tallies_file = openmc.Tallies()
@ -156,7 +155,7 @@ class SurfaceTallyTestHarness(PyAPITestHarness):
surf_tally3.scores = ['current']
tallies_file.append(surf_tally3)
tallies_file.export_to_xml()
self._model.tallies = tallies_file
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
@ -174,5 +173,5 @@ class SurfaceTallyTestHarness(PyAPITestHarness):
def test_surface_tally():
harness = SurfaceTallyTestHarness('statepoint.10.h5')
harness = SurfaceTallyTestHarness('statepoint.10.h5', model=openmc.Model())
harness.main()

View file

@ -1,38 +1,187 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
<model>
<materials>
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector / Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
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</filter>
<filter id="8" type="mu">
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</filter>
<filter id="9" type="polar">
<bins>0.0 0.6283 1.2566 1.885 2.5132 3.14159</bins>
</filter>
<filter id="10" type="legendre">
<order>4</order>
</filter>
<filter cosine="particle" id="11" type="sphericalharmonics">
<order>4</order>
</filter>
<filter id="12" type="universe">
<bins>1 2 3 4 6 8</bins>
</filter>
<filter id="15" type="collision">
<bins>1 2 5 3 6</bins>
</filter>
<filter id="13" type="cell">
<bins>10 21 22 23 60</bins>
</filter>
<filter id="14" type="cell">
<bins>21 22 23 27 28 29 60</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2">
<filters>1</filters>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="4">
<filters>3</filters>
<scores>total</scores>
</tally>
<tally id="5">
<filters>4</filters>
<nuclides>U235 O16 total</nuclides>
<scores>delayed-nu-fission decay-rate</scores>
</tally>
<tally id="6">
<filters>5</filters>
<scores>total</scores>
</tally>
<tally id="7">
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="8">
<filters>5 6</filters>
<scores>scatter nu-fission</scores>
</tally>
<tally id="9">
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="10">
<filters>8</filters>
<scores>scatter nu-scatter</scores>
</tally>
<tally id="11">
<filters>8 2</filters>
<scores>scatter nu-scatter</scores>
</tally>
<tally id="12">
<filters>9</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>9</filters>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="14">
<filters>9 2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="15">
<filters>10</filters>
<scores>scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>11</filters>
<scores>scatter nu-scatter flux total</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>11</filters>
<scores>flux total</scores>
<estimator>collision</estimator>
</tally>
<tally id="18">
<filters>11</filters>
<scores>flux total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="19">
<filters>12</filters>
<scores>total</scores>
</tally>
<tally id="30">
<filters>15</filters>
<scores>scatter</scores>
</tally>
<tally id="20">
<filters>13</filters>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="21">
<filters>13</filters>
<nuclides>U235 O16 total</nuclides>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>13</filters>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable decay-rate</scores>
<estimator>analog</estimator>
</tally>
<tally id="23">
<filters>13</filters>
<nuclides>U235 O16 total</nuclides>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable decay-rate</scores>
<estimator>analog</estimator>
</tally>
<tally id="24">
<filters>13</filters>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable decay-rate</scores>
<estimator>collision</estimator>
</tally>
<tally id="25">
<filters>13</filters>
<nuclides>U235 O16 total</nuclides>
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable decay-rate</scores>
<estimator>collision</estimator>
</tally>
<tally id="26">
<filters>14</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="27">
<filters>14</filters>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>14</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="29">
<scores>H1-production H2-production H3-production He3-production He4-production heating damage-energy</scores>
</tally>
</tallies>
</model>

View file

@ -1,57 +1,56 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="2" region="1" universe="1" />
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<pitch>1.2 1.2</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-1.2 -1.2</lower_left>
<universes>
<model>
<materials>
<material depletable="true" id="1" name="UO2">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
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</material>
<material id="2" name="light water">
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</material>
</materials>
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<pitch>1.2 1.2</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-1.2 -1.2</lower_left>
<universes>
1 1
1 1 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.4" id="1" type="z-cylinder" />
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<?xml version='1.0' encoding='utf-8'?>
<materials>
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</material>
<material id="2" name="light water">
<density units="g/cm3" value="1.0" />
<nuclide ao="2.0" name="H1" />
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</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
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</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1" type="energy">
<bins>0.0 0.253 1000.0 1000000.0 20000000.0</bins>
</filter>
<filter id="2" type="distribcell">
<bins>1</bins>
</filter>
<tally id="1" name="distribcell tally">
<filters>1 2</filters>
<nuclides>U234 U235 U238</nuclides>
<scores>nu-fission total</scores>
</tally>
</tallies>
</lattice>
<surface coeffs="0.0 0.0 0.4" id="1" type="z-cylinder" />
<surface boundary="reflective" coeffs="-1.2" id="2" name="minimum x" type="x-plane" />
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</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
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<filter id="1" type="energy">
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</filter>
<filter id="2" type="distribcell">
<bins>1</bins>
</filter>
<tally id="1" name="distribcell tally">
<filters>1 2</filters>
<nuclides>U234 U235 U238</nuclides>
<scores>nu-fission total</scores>
</tally>
</tallies>
</model>

View file

@ -1,56 +1,55 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
<cell id="2" material="2" region="1 -2" universe="1" />
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<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1">
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</material>
<material id="2" name="light water">
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<nuclide ao="2.0" name="H1" />
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</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
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<inactive>0</inactive>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>2 2</dimension>
<lower_left>-10.0 -10.0</lower_left>
<upper_right>10.0 10.0</upper_right>
</mesh>
<filter id="2" type="material">
<bins>1 2</bins>
</filter>
<filter id="1" type="energy">
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</filter>
<filter id="3" type="mesh">
<bins>1</bins>
</filter>
<tally id="1" name="tally 1">
<filters>2 1</filters>
<nuclides>U234 U235</nuclides>
<scores>nu-fission total</scores>
</tally>
<tally id="2" name="tally 2">
<filters>1 3</filters>
<nuclides>U238 U235</nuclides>
<scores>total fission</scores>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="U234" />
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<material id="2" name="light water">
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<nuclide ao="2.0" name="H1" />
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<sab name="c_H_in_H2O" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1" universe="1" />
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</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
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<inactive>0</inactive>
</settings>
<tallies>
<mesh id="1">
<dimension>2 2</dimension>
<lower_left>-10.0 -10.0</lower_left>
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</mesh>
<filter id="2" type="material">
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</filter>
<filter id="1" type="energy">
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<filter id="3" type="mesh">
<bins>1</bins>
</filter>
<tally id="1" name="tally 1">
<filters>2 1</filters>
<nuclides>U234 U235</nuclides>
<scores>nu-fission total</scores>
</tally>
<tally id="2" name="tally 2">
<filters>1 3</filters>
<nuclides>U238 U235</nuclides>
<scores>total fission</scores>
</tally>
</tallies>
</model>

View file

@ -1,38 +1,187 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
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<model>
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<material id="9" name="Bottom nozzle region">
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<material id="10" name="Top nozzle region">
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<material id="11" name="Top of fuel assemblies">
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1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
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@ -73,12 +222,12 @@
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
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@ -100,12 +249,12 @@
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<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="UOX fuel">
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<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
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<nuclide ao="1.0801e-08" name="Xe135" />
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</material>
<material id="2" name="Zircaloy">
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</material>
<material id="3" name="Cold borated water">
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<nuclide ao="2.0" name="H1" />
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<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
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<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
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<nuclide name="C0" wo="0.0025" />
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<material id="6" name="Lower radial reflector">
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<material id="10" name="Top nozzle region">
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<material id="11" name="Top of fuel assemblies">
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<?xml version='1.0' encoding='utf-8'?>
<tallies>
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<mesh id="1">
<dimension>2 2</dimension>
<lower_left>-50.0 -50.0</lower_left>
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</filter>
<tally id="31" name="cell tally">
<filters>16 8</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="32" name="distribcell tally">
<filters>6 8</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="33" name="mesh tally">
<filters>7 8</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
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<tallies>
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<filter id="7" type="mesh">
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</filter>
<tally id="31" name="cell tally">
<filters>16 8</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="32" name="distribcell tally">
<filters>6 8</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="33" name="mesh tally">
<filters>7 8</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
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</tally>
</tallies>
</model>

View file

@ -1,34 +1,34 @@
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View file

@ -1,37 +1,36 @@
<?xml version='1.0' encoding='utf-8'?>
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View file

@ -1,35 +1,34 @@
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View file

@ -1,442 +1,442 @@
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</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>4</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="point">
<parameters>0.0 0.0 0.0</parameters>
</space>
</source>
</settings>
</model>

View file

@ -9,7 +9,8 @@ from tests.testing_harness import PyAPITestHarness
class TRISOTestHarness(PyAPITestHarness):
def _build_inputs(self):
def __init__(self, *args, **kwargs):
super().__init__(*args, **kwargs)
# Define TRISO matrials
fuel = openmc.Material()
fuel.set_density('g/cm3', 10.5)
@ -78,20 +79,19 @@ class TRISOTestHarness(PyAPITestHarness):
box.fill = lattice
root = openmc.Universe(0, cells=[box])
geom = openmc.Geometry(root)
geom.export_to_xml()
self._model.geometry = openmc.Geometry(root)
settings = openmc.Settings()
settings.batches = 4
settings.inactive = 0
settings.particles = 100
settings.source = openmc.Source(space=openmc.stats.Point())
settings.export_to_xml()
self._model.settings = settings
mats = openmc.Materials([fuel, porous_carbon, ipyc, sic, opyc, graphite])
mats.export_to_xml()
self._model.materials = openmc.Materials([fuel, porous_carbon, ipyc,
sic, opyc, graphite])
def test_triso():
harness = TRISOTestHarness('statepoint.4.h5')
harness = TRISOTestHarness('statepoint.4.h5', model=openmc.Model())
harness.main()

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
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<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_hexes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_hexes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="moab" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_tets_w_holes.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

View file

@ -1,91 +1,90 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="1" material="1" name="fuel" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="2" material="2" name="clad" region="(-1 | 2 | -3 | 4 | -5 | 6) (7 -8 9 -10 11 -12)" universe="1" />
<cell id="3" material="3" name="water" region="(-7 | 8 | -9 | 10 | -11 | 12) (13 -14 15 -16 17 -18)" universe="1" />
<surface coeffs="-5.0" id="1" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="2" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="3" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="4" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="5" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="6" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="7" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="8" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="9" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="10" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="11" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="12" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="13" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="10.0" id="14" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="15" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="10.0" id="16" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="17" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="10.0" id="18" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>1000</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="1">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="2" library="libmesh" type="unstructured">
<filename>test_mesh_tets.e</filename>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<tally id="1" name="regular mesh tally">
<filters>1</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
<tally id="2" name="unstructured mesh tally">
<filters>2</filters>
<scores>flux</scores>
<estimator>collision</estimator>
</tally>
</tallies>
</model>

View file

@ -1,92 +1,91 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="13" material="13" name="fuel" region="73 -74 75 -76 77 -78" universe="5" />
<cell id="14" material="14" name="clad" region="(-73 | 74 | -75 | 76 | -77 | 78) (79 -80 81 -82 83 -84)" universe="5" />
<cell id="15" material="15" name="water" region="(-79 | 80 | -81 | 82 | -83 | 84) (85 -86 87 -88 89 -90)" universe="5" />
<surface coeffs="-5.0" id="73" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="74" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="75" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="76" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="77" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="78" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="79" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="80" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="81" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="82" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="83" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="84" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15" id="85" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15" id="86" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15" id="87" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15" id="88" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15" id="89" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15" id="90" name="maximum z" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="13" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="14" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="15" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<angle reference_uvw="-1.0 0.0 0.0" type="monodirectional" />
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="9">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="10" library="moab" type="unstructured">
<filename>test_mesh_tets_w_holes.exo</filename>
</mesh>
<filter id="9" type="mesh">
<bins>9</bins>
</filter>
<filter id="10" type="mesh">
<bins>10</bins>
</filter>
<tally id="9" name="regular mesh tally">
<filters>9</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10" name="unstructured mesh tally">
<filters>10</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="13" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="14" name="zircaloy">
<density units="g/cc" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="15" name="water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
</materials>
<geometry>
<cell id="13" material="13" name="fuel" region="73 -74 75 -76 77 -78" universe="5" />
<cell id="14" material="14" name="clad" region="(-73 | 74 | -75 | 76 | -77 | 78) (79 -80 81 -82 83 -84)" universe="5" />
<cell id="15" material="15" name="water" region="(-79 | 80 | -81 | 82 | -83 | 84) (85 -86 87 -88 89 -90)" universe="5" />
<surface coeffs="-5.0" id="73" name="minimum x" type="x-plane" />
<surface coeffs="5.0" id="74" name="maximum x" type="x-plane" />
<surface coeffs="-5.0" id="75" name="minimum y" type="y-plane" />
<surface coeffs="5.0" id="76" name="maximum y" type="y-plane" />
<surface coeffs="-5.0" id="77" name="minimum z" type="z-plane" />
<surface coeffs="5.0" id="78" name="maximum z" type="z-plane" />
<surface coeffs="-6.0" id="79" name="minimum x" type="x-plane" />
<surface coeffs="6.0" id="80" name="maximum x" type="x-plane" />
<surface coeffs="-6.0" id="81" name="minimum y" type="y-plane" />
<surface coeffs="6.0" id="82" name="maximum y" type="y-plane" />
<surface coeffs="-6.0" id="83" name="minimum z" type="z-plane" />
<surface coeffs="6.0" id="84" name="maximum z" type="z-plane" />
<surface boundary="vacuum" coeffs="-15" id="85" name="minimum x" type="x-plane" />
<surface boundary="vacuum" coeffs="15" id="86" name="maximum x" type="x-plane" />
<surface boundary="vacuum" coeffs="-15" id="87" name="minimum y" type="y-plane" />
<surface boundary="vacuum" coeffs="15" id="88" name="maximum y" type="y-plane" />
<surface boundary="vacuum" coeffs="-15" id="89" name="minimum z" type="z-plane" />
<surface boundary="vacuum" coeffs="15" id="90" name="maximum z" type="z-plane" />
</geometry>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space origin="0.0 0.0 0.0" type="spherical">
<r parameters="0.0 0.0" type="uniform" />
<cos_theta type="discrete">
<parameters>1.0 1.0</parameters>
</cos_theta>
<phi type="discrete">
<parameters>0.0 1.0</parameters>
</phi>
</space>
<angle reference_uvw="-1.0 0.0 0.0" type="monodirectional" />
<energy type="discrete">
<parameters>15000000.0 1.0</parameters>
</energy>
</source>
</settings>
<tallies>
<mesh id="9">
<dimension>10 10 10</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
<mesh id="10" library="moab" type="unstructured">
<filename>test_mesh_tets_w_holes.exo</filename>
</mesh>
<filter id="9" type="mesh">
<bins>9</bins>
</filter>
<filter id="10" type="mesh">
<bins>10</bins>
</filter>
<tally id="9" name="regular mesh tally">
<filters>9</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10" name="unstructured mesh tally">
<filters>10</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>
</model>

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