Merge pull request #2404 from eepeterson/export_model_xml_on_run

adding export_to_model_xml to model.run
This commit is contained in:
Paul Romano 2023-03-25 15:29:19 -05:00 committed by GitHub
commit ec6f15dfa1
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GPG key ID: 4AEE18F83AFDEB23
177 changed files with 14801 additions and 15430 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

@ -683,11 +683,11 @@ class Plot(IDManagerMixin):
if self._meshlines is not None:
subelement = ET.SubElement(element, "meshlines")
subelement.set("meshtype", self._meshlines['type'])
if self._meshlines['id'] is not None:
if 'id' in self._meshlines:
subelement.set("id", str(self._meshlines['id']))
if self._meshlines['linewidth'] is not None:
if 'linewidth' in self._meshlines:
subelement.set("linewidth", str(self._meshlines['linewidth']))
if self._meshlines['color'] is not None:
if 'color' in self._meshlines:
subelement.set("color", ' '.join(map(
str, self._meshlines['color'])))

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" />
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<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" />
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<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
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<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" />
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<nuclide name="B10" wo="9.44159e-05" />
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<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
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<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" />
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<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>

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@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
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<boundary>reflective</boundary>
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<type>y-plane</type>
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<boundary>reflective</boundary>
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</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

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@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
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<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
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<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
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<filter id="1" type="mesh">
<bins>1</bins>
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<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
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<entropy_mesh>10</entropy_mesh>
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
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<boundary>reflective</boundary>
</surface>
</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

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@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
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<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
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<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
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<filter id="1" type="mesh">
<bins>1</bins>
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<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
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<entropy_mesh>10</entropy_mesh>
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
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<filter id="1">
<type>mesh</type>
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<tally id="1">
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<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
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<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
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<boundary>reflective</boundary>
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<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
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<boundary>reflective</boundary>
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</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

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@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
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<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
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</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
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<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
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<tallies>
<mesh id="1">
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<lower_left>-10.0 -1.0 -1.0</lower_left>
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<filter id="1" type="mesh">
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<tally id="1">
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<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
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</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
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<lower_left>-10 -1 -1 </lower_left>
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<type>mesh</type>
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<scores>flux</scores>
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</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
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<surface id="2">
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<boundary> vacuum </boundary>
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<boundary>reflective</boundary>
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<boundary>reflective</boundary>
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</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

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@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
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<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
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</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
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<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
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<tallies>
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<tally id="1">
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<scores>flux</scores>
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</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
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<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
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View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
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<tally id="1">
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<scores>flux</scores>
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</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
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<surface id="2">
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<boundary> vacuum </boundary>
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<boundary>reflective</boundary>
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<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

View file

@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

View file

@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

View file

@ -0,0 +1,54 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<state_point>
<batches>15 20</batches>
</state_point>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,28 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
<state_point batches="15 20" />
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

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" />
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<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

@ -1,23 +0,0 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="5" id="1" name="Cell 1" region="1 -2 3 -4" universe="0" />
<cell id="101" material="1" name="cell 2" region="-5" universe="1" />
<cell id="102" material="2" name="cell 3" region="5" universe="1" />
<cell id="500" material="2" name="cell 4" region="" universe="3" />
<hex_lattice id="5" n_rings="2">
<pitch>1.0</pitch>
<outer>3</outer>
<center>0.0 0.0</center>
<universes>
1
1 1
1
1 1
1</universes>
</hex_lattice>
<surface boundary="vacuum" coeffs="-3" id="1" name="left" type="x-plane" />
<surface boundary="vacuum" coeffs="3" id="2" name="right" type="x-plane" />
<surface boundary="vacuum" coeffs="-4" id="3" name="bottom" type="y-plane" />
<surface boundary="vacuum" coeffs="4" id="4" name="top" type="y-plane" />
<surface boundary="transmission" coeffs="0 0 0.4" id="5" type="z-cylinder" />
</geometry>

View file

@ -1,19 +0,0 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="moderator">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="2.0" name="H1" />
<sab name="c_H_in_H2O" />
</material>
<material id="3" name="iron">
<density units="g/cc" value="7.9" />
<nuclide ao="1.0" name="Fe56" />
</material>
</materials>

View file

@ -0,0 +1,61 @@
<?xml version='1.0' encoding='utf-8'?>
<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="moderator">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="2.0" name="H1" />
<sab name="c_H_in_H2O" />
</material>
<material id="3" name="iron">
<density units="g/cc" value="7.9" />
<nuclide ao="1.0" name="Fe56" />
</material>
</materials>
<geometry>
<cell fill="5" id="1" name="Cell 1" region="1 -2 3 -4" universe="0" />
<cell id="101" material="1" name="cell 2" region="-5" universe="1" />
<cell id="102" material="2" name="cell 3" region="5" universe="1" />
<cell id="500" material="2" name="cell 4" universe="3" />
<hex_lattice id="5" n_rings="2">
<pitch>1.0</pitch>
<outer>3</outer>
<center>0.0 0.0</center>
<universes>
1
1 1
1
1 1
1</universes>
</hex_lattice>
<surface boundary="vacuum" coeffs="-3.0" id="1" name="left" type="x-plane" />
<surface boundary="vacuum" coeffs="3.0" id="2" name="right" type="x-plane" />
<surface boundary="vacuum" coeffs="-4.0" id="3" name="bottom" type="y-plane" />
<surface boundary="vacuum" coeffs="4.0" id="4" name="top" type="y-plane" />
<surface coeffs="0.0 0.0 0.4" id="5" type="z-cylinder" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>1</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-1.0 -1.0 -1.0 1.0 1.0 1.0</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="distribcell">
<bins>101</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
</model>

View file

@ -1,12 +0,0 @@
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>1</batches>
<inactive>0</inactive>
<source>
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>

View file

@ -1,14 +0,0 @@
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1">
<type>distribcell</type>
<bins>101</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>

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>
<filter id="5" 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-linear</interpolation>
</filter>
<filter id="6" type="energyfunction">
<energy>0.0 5000000.0 10000000.0 15000000.0</energy>
<y>0.2 0.7 0.7 0.2</y>
<interpolation>linear-linear</interpolation>
</filter>
<filter id="7" type="energyfunction">
<energy>0.0 5000000.0 10000000.0 15000000.0</energy>
<y>0.2 0.7 0.7 0.2</y>
<interpolation>quadratic</interpolation>
</filter>
<filter id="8" type="energyfunction">
<energy>0.0 5000000.0 10000000.0 15000000.0</energy>
<y>0.2 0.7 0.7 0.2</y>
<interpolation>cubic</interpolation>
</filter>
<filter id="9" type="energyfunction">
<energy>0.0 5000000.0 10000000.0 15000000.0</energy>
<y>0.2 0.7 0.7 0.2</y>
<interpolation>histogram</interpolation>
</filter>
<tally id="1">
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="2">
<filters>1</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="3">
<filters>3</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="4">
<filters>4</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="5">
<filters>5</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="6">
<filters>6</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="7">
<filters>7</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="8">
<filters>8</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="9">
<filters>9</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
</tallies>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cm3" value="10.0" />
<nuclide ao="1.0" name="Am241" />
</material>
</materials>
<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>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
</settings>
<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>
<filter id="5" 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-linear</interpolation>
</filter>
<filter id="6" type="energyfunction">
<energy>0.0 5000000.0 10000000.0 15000000.0</energy>
<y>0.2 0.7 0.7 0.2</y>
<interpolation>linear-linear</interpolation>
</filter>
<filter id="7" type="energyfunction">
<energy>0.0 5000000.0 10000000.0 15000000.0</energy>
<y>0.2 0.7 0.7 0.2</y>
<interpolation>quadratic</interpolation>
</filter>
<filter id="8" type="energyfunction">
<energy>0.0 5000000.0 10000000.0 15000000.0</energy>
<y>0.2 0.7 0.7 0.2</y>
<interpolation>cubic</interpolation>
</filter>
<filter id="9" type="energyfunction">
<energy>0.0 5000000.0 10000000.0 15000000.0</energy>
<y>0.2 0.7 0.7 0.2</y>
<interpolation>histogram</interpolation>
</filter>
<tally id="1">
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="2">
<filters>1</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="3">
<filters>3</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="4">
<filters>4</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="5">
<filters>5</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="6">
<filters>6</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="7">
<filters>7</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="8">
<filters>8</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="9">
<filters>9</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
</tallies>
</model>

View file

@ -1,152 +1,151 @@
<?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>5</dimension>
<lower_left>-7.5</lower_left>
<upper_right>7.5</upper_right>
</mesh>
<mesh id="2">
<dimension>5 5</dimension>
<lower_left>-7.5 -7.5</lower_left>
<upper_right>7.5 7.5</upper_right>
</mesh>
<mesh id="3">
<dimension>5 5 5</dimension>
<lower_left>-7.5 -7.5 -7.5</lower_left>
<upper_right>7.5 7.5 7.5</upper_right>
</mesh>
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View file

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View file

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View file

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<materials>
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U238" />
</material>
</materials>
<geometry>
<cell id="11" material="1" universe="11" />
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<cell fill="21" id="101" region="-101" universe="0" />
<lattice id="21">
<pitch>2.0 2.0</pitch>
<outer>12</outer>
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<universes>
11 12
12 11 </universes>
</lattice>
<surface boundary="vacuum" coeffs="0.0 0.0 5.0" id="101" type="z-cylinder" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4.0 -4.0 -4.0 4.0 4.0 4.0</parameters>
</space>
</source>
</settings>
</model>

View file

@ -1,15 +0,0 @@
<?xml version="1.0"?>
<settings>
<run_mode>eigenvalue</run_mode>
<batches>10</batches>
<inactive>5</inactive>
<particles>1000</particles>
<source>
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>

View file

@ -1,38 +1,199 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
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<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" />
<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" />
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<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>
<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" />
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<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" />
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<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
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<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 +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>
</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 +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>
</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 +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>
</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
@ -127,195 +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

@ -1,297 +1,296 @@
import openmc
import numpy as np
names = ['H', 'O', 'Zr', 'U235', 'U238']
def build_openmc_xs_lib(name, groups, temperatures, xsdict, micro=True):
"""Build an Openm XSdata based on dictionary values"""
xsdata = openmc.XSdata(name, groups, temperatures=temperatures)
xsdata.order = 0
for tt in temperatures:
xsdata.set_absorption(xsdict[tt]['absorption'][name], temperature=tt)
xsdata.set_scatter_matrix(xsdict[tt]['scatter'][name], temperature=tt)
xsdata.set_total(xsdict[tt]['total'][name], temperature=tt)
if (name in xsdict[tt]['nu-fission'].keys()):
xsdata.set_nu_fission(xsdict[tt]['nu-fission'][name],
temperature=tt)
xsdata.set_chi(np.array([1., 0.]), temperature=tt)
return xsdata
def create_micro_xs_dict():
"""Returns micro xs library"""
xs_micro = {}
reactions = ['absorption', 'total', 'scatter', 'nu-fission']
# chi is unnecessary when energy bound is in thermal region
# Temperature 300K
# absorption
xs_micro[300] = {r: {} for r in reactions}
xs_micro[300]['absorption']['H'] = np.array([1.0285E-4, 0.0057])
xs_micro[300]['absorption']['O'] = np.array([7.1654E-5, 3.0283E-6])
xs_micro[300]['absorption']['Zr'] = np.array([4.5918E-5, 3.6303E-5])
xs_micro[300]['absorption']['U235'] = np.array([0.0035, 0.1040])
xs_micro[300]['absorption']['U238'] = np.array([0.0056, 0.0094])
# nu-scatter matrix
xs_micro[300]['scatter']['H'] = np.array([[[0.0910, 0.01469],
[0.0, 0.3316]]])
xs_micro[300]['scatter']['O'] = np.array([[[0.0814, 3.3235E-4],
[0.0, 0.0960]]])
xs_micro[300]['scatter']['Zr'] = np.array([[[0.0311, 2.6373E-5],
[0.0, 0.0315]]])
xs_micro[300]['scatter']['U235'] = np.array([[[0.0311, 2.6373E-5],
[0.0, 0.0315]]])
xs_micro[300]['scatter']['U238'] = np.array([[[0.0551, 2.2341E-5],
[0.0, 0.0526]]])
# nu-fission
xs_micro[300]['nu-fission']['U235'] = np.array([0.0059, 0.2160])
xs_micro[300]['nu-fission']['U238'] = np.array([0.0019, 1.4627E-7])
# total
xs_micro[300]['total']['H'] = xs_micro[300]['absorption']['H'] + \
np.sum(xs_micro[300]['scatter']['H'][0], 1)
xs_micro[300]['total']['O'] = xs_micro[300]['absorption']['O'] + \
np.sum(xs_micro[300]['scatter']['O'][0], 1)
xs_micro[300]['total']['Zr'] = xs_micro[300]['absorption']['Zr'] + \
np.sum(xs_micro[300]['scatter']['Zr'][0], 1)
xs_micro[300]['total']['U235'] = xs_micro[300]['absorption']['U235'] + \
np.sum(xs_micro[300]['scatter']['U235'][0], 1)
xs_micro[300]['total']['U238'] = xs_micro[300]['absorption']['U238'] + \
np.sum(xs_micro[300]['scatter']['U238'][0], 1)
# Temperature 600K
xs_micro[600] = {r: {} for r in reactions}
# absorption
xs_micro[600]['absorption']['H'] = np.array([1.0356E-4, 0.0046])
xs_micro[600]['absorption']['O'] = np.array([7.2678E-5, 2.4963E-6])
xs_micro[600]['absorption']['Zr'] = np.array([4.7256E-5, 2.9757E-5])
xs_micro[600]['absorption']['U235'] = np.array([0.0035, 0.0853])
xs_micro[600]['absorption']['U238'] = np.array([0.0058, 0.0079])
# nu-scatter matrix
xs_micro[600]['scatter']['H'] = np.array([[[0.0910, 0.0138],
[0.0, 0.3316]]])
xs_micro[600]['scatter']['O'] = np.array([[[0.0814, 3.5367E-4],
[0.0, 0.0959]]])
xs_micro[600]['scatter']['Zr'] = np.array([[[0.0311, 3.2293E-5],
[0.0, 0.0314]]])
xs_micro[600]['scatter']['U235'] = np.array([[[0.0022, 1.9763E-6],
[9.1634E-8, 0.0039]]])
xs_micro[600]['scatter']['U238'] = np.array([[[0.0556, 2.8803E-5],
[0.0, 0.0536]]])
# nu-fission
xs_micro[600]['nu-fission']['U235'] = np.array([0.0059, 0.1767])
xs_micro[600]['nu-fission']['U238'] = np.array([0.0019, 1.2405E-7])
# total
xs_micro[600]['total']['H'] = xs_micro[600]['absorption']['H'] + \
np.sum(xs_micro[600]['scatter']['H'][0], 1)
xs_micro[600]['total']['O'] = xs_micro[600]['absorption']['O'] + \
np.sum(xs_micro[600]['scatter']['O'][0], 1)
xs_micro[600]['total']['Zr'] = xs_micro[600]['absorption']['Zr'] + \
np.sum(xs_micro[600]['scatter']['Zr'][0], 1)
xs_micro[600]['total']['U235'] = xs_micro[600]['absorption']['U235'] + \
np.sum(xs_micro[600]['scatter']['U235'][0], 1)
xs_micro[600]['total']['U238'] = xs_micro[600]['absorption']['U238'] + \
np.sum(xs_micro[600]['scatter']['U238'][0], 1)
# Temperature 900K
xs_micro[900] = {r: {} for r in reactions}
# absorption
xs_micro[900]['absorption']['H'] = np.array([1.0529E-4, 0.0040])
xs_micro[900]['absorption']['O'] = np.array([7.3055E-5, 2.1850E-6])
xs_micro[900]['absorption']['Zr'] = np.array([4.7141E-5, 2.5941E-5])
xs_micro[900]['absorption']['U235'] = np.array([0.0035, 0.0749])
xs_micro[900]['absorption']['U238'] = np.array([0.0060, 0.0071])
# total
xs_micro[900]['total']['H'] = np.array([0.2982, 0.7332])
xs_micro[900]['total']['O'] = np.array([0.0885, 0.1004])
xs_micro[900]['total']['Zr'] = np.array([0.0370, 0.0317])
xs_micro[900]['total']['U235'] = np.array([0.0061, 0.0789])
xs_micro[900]['total']['U238'] = np.array([0.0707, 0.0613])
# nu-scatter matrix
xs_micro[900]['scatter']['H'] = np.array([[[0.0913, 0.0147],
[0.0, 0.4020]]])
xs_micro[900]['scatter']['O'] = np.array([[[0.0812, 4.0413E-4],
[0.0, 0.0965]]])
xs_micro[900]['scatter']['Zr'] = np.array([[[0.0311, 3.6735E-5],
[0.0, 0.0314]]])
xs_micro[900]['scatter']['U235'] = np.array([[[0.0022, 2.9034E-6],
[1.3117E-8, 0.0039]]])
xs_micro[900]['scatter']['U238'] = np.array([[[0.0560, 3.7619E-5],
[0.0, 0.0538]]])
# nu-fission
xs_micro[900]['nu-fission']['U235'] = np.array([0.0059, 0.1545])
xs_micro[900]['nu-fission']['U238'] = np.array([0.0019, 1.1017E-7])
# total
xs_micro[900]['total']['H'] = xs_micro[900]['absorption']['H'] + \
np.sum(xs_micro[900]['scatter']['H'][0], 1)
xs_micro[900]['total']['O'] = xs_micro[900]['absorption']['O'] + \
np.sum(xs_micro[900]['scatter']['O'][0], 1)
xs_micro[900]['total']['Zr'] = xs_micro[900]['absorption']['Zr'] + \
np.sum(xs_micro[900]['scatter']['Zr'][0], 1)
xs_micro[900]['total']['U235'] = xs_micro[900]['absorption']['U235'] + \
np.sum(xs_micro[900]['scatter']['U235'][0], 1)
xs_micro[900]['total']['U238'] = xs_micro[900]['absorption']['U238'] + \
np.sum(xs_micro[900]['scatter']['U238'][0], 1)
# roll axis for scatter matrix
for t in xs_micro:
for n in xs_micro[t]['scatter']:
xs_micro[t]['scatter'][n] = np.rollaxis(xs_micro[t]['scatter'][n],
0, 3)
return xs_micro
def create_macro_dict(xs_micro):
"""Create a dictionary with two group cross-section"""
xs_macro = {}
for t, d1 in xs_micro.items():
xs_macro[t] = {}
for r, d2 in d1.items():
temp = []
xs_macro[t][r] = {}
for n, v in d2.items():
temp.append(d2[n])
# The name 'macro' is needed to store data at the same level
# of a xs_macro dictionary as for xs_micro and use it in
# function build_openmc_xs_lib
xs_macro[t][r]['macro'] = sum(temp)
return xs_macro
def create_openmc_2mg_libs(names):
"""Built a micro/macro two group openmc MGXS libraries"""
# Initialized library params
group_edges = [0.0, 0.625, 20.0e6]
groups = openmc.mgxs.EnergyGroups(group_edges=group_edges)
mg_cross_sections_file_micro = openmc.MGXSLibrary(groups)
mg_cross_sections_file_macro = openmc.MGXSLibrary(groups)
# Building a micro mg library
micro_cs = create_micro_xs_dict()
for name in names:
mg_cross_sections_file_micro.add_xsdata(build_openmc_xs_lib(name,
groups,
[t for t in
micro_cs],
micro_cs))
# Building a macro mg library
macro_xs = create_macro_dict(micro_cs)
mg_cross_sections_file_macro.add_xsdata(build_openmc_xs_lib('macro',
groups,
[t for t in
macro_xs],
macro_xs))
# Exporting library to hdf5 files
mg_cross_sections_file_micro.export_to_hdf5('micro_2g.h5')
mg_cross_sections_file_macro.export_to_hdf5('macro_2g.h5')
# Returning the macro_xs dict is needed for analytical solution
return macro_xs
def analytical_solution_2g_therm(xsmin, xsmax=None, wgt=1.0):
""" Calculate eigenvalue based on analytical solution for eq Lf = (1/k)Qf
in two group for infinity dilution media in assumption of group
boundary in thermal spectra < 1.e+3 Ev
Parameters:
----------
xsmin : dict
macro cross-sections dictionary with minimum range temperature
xsmax : dict
macro cross-sections dictionary with maximum range temperature
by default: None not used for standalone temperature
wgt : float
weight for interpolation by default 1.0
Returns:
-------
keff : np.float64
analytical eigenvalue of critical eq matrix
"""
if xsmax is None:
sa = xsmin['absorption']['macro']
ss12 = xsmin['scatter']['macro'][0][1][0]
nsf = xsmin['nu-fission']['macro']
else:
sa = xsmin['absorption']['macro'] * wgt + \
xsmax['absorption']['macro'] * (1 - wgt)
ss12 = xsmin['scatter']['macro'][0][1][0] * wgt + \
xsmax['scatter']['macro'][0][1][0] * (1 - wgt)
nsf = xsmin['nu-fission']['macro'] * wgt + \
xsmax['nu-fission']['macro'] * (1 - wgt)
L = np.array([sa[0] + ss12, 0.0, -ss12, sa[1]]).reshape(2, 2)
Q = np.array([nsf[0], nsf[1], 0.0, 0.0]).reshape(2, 2)
arr = np.linalg.inv(L).dot(Q)
return np.amax(np.linalg.eigvals(arr))
def build_inf_model(xsnames, xslibname, temperature, tempmethod='nearest'):
""" Building an infinite medium for openmc multi-group testing
Parameters:
----------
xsnames : list of str()
list with xs names
xslibname:
name of hdf5 file with cross-section library
temperature : float
value of a current temperature in K
tempmethod : {'nearest', 'interpolation'}
by default 'nearest'
"""
inf_medium = openmc.Material(name='test material', material_id=1)
inf_medium.set_density("sum")
for xs in xsnames:
inf_medium.add_nuclide(xs, 1)
INF = 11.1
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([inf_medium])
materials_file.cross_sections = xslibname
materials_file.export_to_xml()
# Instantiate boundary Planes
min_x = openmc.XPlane(boundary_type='reflective', x0=-INF)
max_x = openmc.XPlane(boundary_type='reflective', x0=INF)
min_y = openmc.YPlane(boundary_type='reflective', y0=-INF)
max_y = openmc.YPlane(boundary_type='reflective', y0=INF)
# Instantiate a Cell
cell = openmc.Cell(cell_id=1, name='cell')
cell.temperature = temperature
# Register bounding Surfaces with the Cell
cell.region = +min_x & -max_x & +min_y & -max_y
# Fill the Cell with the Material
cell.fill = inf_medium
# Create root universe
root_universe = openmc.Universe(name='root universe', cells=[cell])
# Create Geometry and set root Universe
openmc_geometry = openmc.Geometry(root_universe)
# Export to "geometry.xml"
openmc_geometry.export_to_xml()
# OpenMC simulation parameters
batches = 200
inactive = 5
particles = 5000
# Instantiate a Settings object
settings_file = openmc.Settings()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.energy_mode = 'multi-group'
settings_file.output = {'summary': False}
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-INF, -INF, -INF, INF, INF, INF]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.temperature = {'method': tempmethod}
settings_file.source = openmc.Source(space=uniform_dist)
settings_file.export_to_xml()
import openmc
import numpy as np
names = ['H', 'O', 'Zr', 'U235', 'U238']
def build_openmc_xs_lib(name, groups, temperatures, xsdict, micro=True):
"""Build an Openm XSdata based on dictionary values"""
xsdata = openmc.XSdata(name, groups, temperatures=temperatures)
xsdata.order = 0
for tt in temperatures:
xsdata.set_absorption(xsdict[tt]['absorption'][name], temperature=tt)
xsdata.set_scatter_matrix(xsdict[tt]['scatter'][name], temperature=tt)
xsdata.set_total(xsdict[tt]['total'][name], temperature=tt)
if (name in xsdict[tt]['nu-fission'].keys()):
xsdata.set_nu_fission(xsdict[tt]['nu-fission'][name],
temperature=tt)
xsdata.set_chi(np.array([1., 0.]), temperature=tt)
return xsdata
def create_micro_xs_dict():
"""Returns micro xs library"""
xs_micro = {}
reactions = ['absorption', 'total', 'scatter', 'nu-fission']
# chi is unnecessary when energy bound is in thermal region
# Temperature 300K
# absorption
xs_micro[300] = {r: {} for r in reactions}
xs_micro[300]['absorption']['H'] = np.array([1.0285E-4, 0.0057])
xs_micro[300]['absorption']['O'] = np.array([7.1654E-5, 3.0283E-6])
xs_micro[300]['absorption']['Zr'] = np.array([4.5918E-5, 3.6303E-5])
xs_micro[300]['absorption']['U235'] = np.array([0.0035, 0.1040])
xs_micro[300]['absorption']['U238'] = np.array([0.0056, 0.0094])
# nu-scatter matrix
xs_micro[300]['scatter']['H'] = np.array([[[0.0910, 0.01469],
[0.0, 0.3316]]])
xs_micro[300]['scatter']['O'] = np.array([[[0.0814, 3.3235E-4],
[0.0, 0.0960]]])
xs_micro[300]['scatter']['Zr'] = np.array([[[0.0311, 2.6373E-5],
[0.0, 0.0315]]])
xs_micro[300]['scatter']['U235'] = np.array([[[0.0311, 2.6373E-5],
[0.0, 0.0315]]])
xs_micro[300]['scatter']['U238'] = np.array([[[0.0551, 2.2341E-5],
[0.0, 0.0526]]])
# nu-fission
xs_micro[300]['nu-fission']['U235'] = np.array([0.0059, 0.2160])
xs_micro[300]['nu-fission']['U238'] = np.array([0.0019, 1.4627E-7])
# total
xs_micro[300]['total']['H'] = xs_micro[300]['absorption']['H'] + \
np.sum(xs_micro[300]['scatter']['H'][0], 1)
xs_micro[300]['total']['O'] = xs_micro[300]['absorption']['O'] + \
np.sum(xs_micro[300]['scatter']['O'][0], 1)
xs_micro[300]['total']['Zr'] = xs_micro[300]['absorption']['Zr'] + \
np.sum(xs_micro[300]['scatter']['Zr'][0], 1)
xs_micro[300]['total']['U235'] = xs_micro[300]['absorption']['U235'] + \
np.sum(xs_micro[300]['scatter']['U235'][0], 1)
xs_micro[300]['total']['U238'] = xs_micro[300]['absorption']['U238'] + \
np.sum(xs_micro[300]['scatter']['U238'][0], 1)
# Temperature 600K
xs_micro[600] = {r: {} for r in reactions}
# absorption
xs_micro[600]['absorption']['H'] = np.array([1.0356E-4, 0.0046])
xs_micro[600]['absorption']['O'] = np.array([7.2678E-5, 2.4963E-6])
xs_micro[600]['absorption']['Zr'] = np.array([4.7256E-5, 2.9757E-5])
xs_micro[600]['absorption']['U235'] = np.array([0.0035, 0.0853])
xs_micro[600]['absorption']['U238'] = np.array([0.0058, 0.0079])
# nu-scatter matrix
xs_micro[600]['scatter']['H'] = np.array([[[0.0910, 0.0138],
[0.0, 0.3316]]])
xs_micro[600]['scatter']['O'] = np.array([[[0.0814, 3.5367E-4],
[0.0, 0.0959]]])
xs_micro[600]['scatter']['Zr'] = np.array([[[0.0311, 3.2293E-5],
[0.0, 0.0314]]])
xs_micro[600]['scatter']['U235'] = np.array([[[0.0022, 1.9763E-6],
[9.1634E-8, 0.0039]]])
xs_micro[600]['scatter']['U238'] = np.array([[[0.0556, 2.8803E-5],
[0.0, 0.0536]]])
# nu-fission
xs_micro[600]['nu-fission']['U235'] = np.array([0.0059, 0.1767])
xs_micro[600]['nu-fission']['U238'] = np.array([0.0019, 1.2405E-7])
# total
xs_micro[600]['total']['H'] = xs_micro[600]['absorption']['H'] + \
np.sum(xs_micro[600]['scatter']['H'][0], 1)
xs_micro[600]['total']['O'] = xs_micro[600]['absorption']['O'] + \
np.sum(xs_micro[600]['scatter']['O'][0], 1)
xs_micro[600]['total']['Zr'] = xs_micro[600]['absorption']['Zr'] + \
np.sum(xs_micro[600]['scatter']['Zr'][0], 1)
xs_micro[600]['total']['U235'] = xs_micro[600]['absorption']['U235'] + \
np.sum(xs_micro[600]['scatter']['U235'][0], 1)
xs_micro[600]['total']['U238'] = xs_micro[600]['absorption']['U238'] + \
np.sum(xs_micro[600]['scatter']['U238'][0], 1)
# Temperature 900K
xs_micro[900] = {r: {} for r in reactions}
# absorption
xs_micro[900]['absorption']['H'] = np.array([1.0529E-4, 0.0040])
xs_micro[900]['absorption']['O'] = np.array([7.3055E-5, 2.1850E-6])
xs_micro[900]['absorption']['Zr'] = np.array([4.7141E-5, 2.5941E-5])
xs_micro[900]['absorption']['U235'] = np.array([0.0035, 0.0749])
xs_micro[900]['absorption']['U238'] = np.array([0.0060, 0.0071])
# total
xs_micro[900]['total']['H'] = np.array([0.2982, 0.7332])
xs_micro[900]['total']['O'] = np.array([0.0885, 0.1004])
xs_micro[900]['total']['Zr'] = np.array([0.0370, 0.0317])
xs_micro[900]['total']['U235'] = np.array([0.0061, 0.0789])
xs_micro[900]['total']['U238'] = np.array([0.0707, 0.0613])
# nu-scatter matrix
xs_micro[900]['scatter']['H'] = np.array([[[0.0913, 0.0147],
[0.0, 0.4020]]])
xs_micro[900]['scatter']['O'] = np.array([[[0.0812, 4.0413E-4],
[0.0, 0.0965]]])
xs_micro[900]['scatter']['Zr'] = np.array([[[0.0311, 3.6735E-5],
[0.0, 0.0314]]])
xs_micro[900]['scatter']['U235'] = np.array([[[0.0022, 2.9034E-6],
[1.3117E-8, 0.0039]]])
xs_micro[900]['scatter']['U238'] = np.array([[[0.0560, 3.7619E-5],
[0.0, 0.0538]]])
# nu-fission
xs_micro[900]['nu-fission']['U235'] = np.array([0.0059, 0.1545])
xs_micro[900]['nu-fission']['U238'] = np.array([0.0019, 1.1017E-7])
# total
xs_micro[900]['total']['H'] = xs_micro[900]['absorption']['H'] + \
np.sum(xs_micro[900]['scatter']['H'][0], 1)
xs_micro[900]['total']['O'] = xs_micro[900]['absorption']['O'] + \
np.sum(xs_micro[900]['scatter']['O'][0], 1)
xs_micro[900]['total']['Zr'] = xs_micro[900]['absorption']['Zr'] + \
np.sum(xs_micro[900]['scatter']['Zr'][0], 1)
xs_micro[900]['total']['U235'] = xs_micro[900]['absorption']['U235'] + \
np.sum(xs_micro[900]['scatter']['U235'][0], 1)
xs_micro[900]['total']['U238'] = xs_micro[900]['absorption']['U238'] + \
np.sum(xs_micro[900]['scatter']['U238'][0], 1)
# roll axis for scatter matrix
for t in xs_micro:
for n in xs_micro[t]['scatter']:
xs_micro[t]['scatter'][n] = np.rollaxis(xs_micro[t]['scatter'][n],
0, 3)
return xs_micro
def create_macro_dict(xs_micro):
"""Create a dictionary with two group cross-section"""
xs_macro = {}
for t, d1 in xs_micro.items():
xs_macro[t] = {}
for r, d2 in d1.items():
temp = []
xs_macro[t][r] = {}
for n, v in d2.items():
temp.append(d2[n])
# The name 'macro' is needed to store data at the same level
# of a xs_macro dictionary as for xs_micro and use it in
# function build_openmc_xs_lib
xs_macro[t][r]['macro'] = sum(temp)
return xs_macro
def create_openmc_2mg_libs(names):
"""Built a micro/macro two group openmc MGXS libraries"""
# Initialized library params
group_edges = [0.0, 0.625, 20.0e6]
groups = openmc.mgxs.EnergyGroups(group_edges=group_edges)
mg_cross_sections_file_micro = openmc.MGXSLibrary(groups)
mg_cross_sections_file_macro = openmc.MGXSLibrary(groups)
# Building a micro mg library
micro_cs = create_micro_xs_dict()
for name in names:
mg_cross_sections_file_micro.add_xsdata(build_openmc_xs_lib(name,
groups,
[t for t in
micro_cs],
micro_cs))
# Building a macro mg library
macro_xs = create_macro_dict(micro_cs)
mg_cross_sections_file_macro.add_xsdata(build_openmc_xs_lib('macro',
groups,
[t for t in
macro_xs],
macro_xs))
# Exporting library to hdf5 files
mg_cross_sections_file_micro.export_to_hdf5('micro_2g.h5')
mg_cross_sections_file_macro.export_to_hdf5('macro_2g.h5')
# Returning the macro_xs dict is needed for analytical solution
return macro_xs
def analytical_solution_2g_therm(xsmin, xsmax=None, wgt=1.0):
""" Calculate eigenvalue based on analytical solution for eq Lf = (1/k)Qf
in two group for infinity dilution media in assumption of group
boundary in thermal spectra < 1.e+3 Ev
Parameters:
----------
xsmin : dict
macro cross-sections dictionary with minimum range temperature
xsmax : dict
macro cross-sections dictionary with maximum range temperature
by default: None not used for standalone temperature
wgt : float
weight for interpolation by default 1.0
Returns:
-------
keff : np.float64
analytical eigenvalue of critical eq matrix
"""
if xsmax is None:
sa = xsmin['absorption']['macro']
ss12 = xsmin['scatter']['macro'][0][1][0]
nsf = xsmin['nu-fission']['macro']
else:
sa = xsmin['absorption']['macro'] * wgt + \
xsmax['absorption']['macro'] * (1 - wgt)
ss12 = xsmin['scatter']['macro'][0][1][0] * wgt + \
xsmax['scatter']['macro'][0][1][0] * (1 - wgt)
nsf = xsmin['nu-fission']['macro'] * wgt + \
xsmax['nu-fission']['macro'] * (1 - wgt)
L = np.array([sa[0] + ss12, 0.0, -ss12, sa[1]]).reshape(2, 2)
Q = np.array([nsf[0], nsf[1], 0.0, 0.0]).reshape(2, 2)
arr = np.linalg.inv(L).dot(Q)
return np.amax(np.linalg.eigvals(arr))
def build_inf_model(xsnames, xslibname, temperature, tempmethod='nearest'):
""" Building an infinite medium for openmc multi-group testing
Parameters:
----------
xsnames : list of str()
list with xs names
xslibname:
name of hdf5 file with cross-section library
temperature : float
value of a current temperature in K
tempmethod : {'nearest', 'interpolation'}
by default 'nearest'
"""
model = openmc.Model()
inf_medium = openmc.Material(name='test material', material_id=1)
inf_medium.set_density("sum")
for xs in xsnames:
inf_medium.add_nuclide(xs, 1)
INF = 11.1
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([inf_medium])
materials_file.cross_sections = xslibname
model.materials = materials_file
# Instantiate boundary Planes
min_x = openmc.XPlane(boundary_type='reflective', x0=-INF)
max_x = openmc.XPlane(boundary_type='reflective', x0=INF)
min_y = openmc.YPlane(boundary_type='reflective', y0=-INF)
max_y = openmc.YPlane(boundary_type='reflective', y0=INF)
# Instantiate a Cell
cell = openmc.Cell(cell_id=1, name='cell')
cell.temperature = temperature
# Register bounding Surfaces with the Cell
cell.region = +min_x & -max_x & +min_y & -max_y
# Fill the Cell with the Material
cell.fill = inf_medium
# Create root universe
root_universe = openmc.Universe(name='root universe', cells=[cell])
# Create Geometry and set root Universe
model.geometry = openmc.Geometry(root_universe)
# OpenMC simulation parameters
batches = 200
inactive = 5
particles = 5000
# Instantiate a Settings object
settings_file = openmc.Settings()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.energy_mode = 'multi-group'
settings_file.output = {'summary': False}
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-INF, -INF, -INF, INF, INF, INF]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.temperature = {'method': tempmethod}
settings_file.source = openmc.Source(space=uniform_dist)
model.settings = settings_file
model.export_to_model_xml()

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>
<tally id="15">
<filters>17 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="17">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="18">
<filters>17 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="20">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="21">
<filters>17 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="22">
<filters>17 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="23">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="24">
<filters>33 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="25">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="26">
<filters>33 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="28">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="29">
<filters>33 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="31">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="32">
<filters>33 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="33">
<filters>33 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-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>
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<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>
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<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
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<tally id="6">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
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<tally id="7">
<filters>1 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
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<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>
<tally id="15">
<filters>17 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="17">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="18">
<filters>17 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="20">
<filters>17 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="21">
<filters>17 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="22">
<filters>17 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="23">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="24">
<filters>33 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="25">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="26">
<filters>33 2 3 4</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="28">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="29">
<filters>33 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
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<tally id="30">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="31">
<filters>33 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="32">
<filters>33 2 3 4</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="33">
<filters>33 2 3</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
</tallies>
</model>

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