-
Notifications
You must be signed in to change notification settings - Fork 623
Open
Description
Bug Description
OpenMC currently exhibits undefined behavior (typically seg faults) when the new surface tallies from #3742 are used on a model with a lattice.
Steps to Reproduce
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1" depletable="true">
<density value="10.0" units="g/cm3"/>
<nuclide name="U235" ao="0.04"/>
<nuclide name="U238" ao="0.96"/>
<nuclide name="O16" ao="2.0"/>
</material>
</materials>
<geometry>
<cell id="1" material="1" universe="1"/>
<cell id="2" material="1" universe="2"/>
<cell id="3" material="1" universe="3"/>
<cell id="4" material="1" universe="4"/>
<cell id="5" material="1" universe="5"/>
<cell id="6" material="1" universe="6"/>
<cell id="7" material="1" universe="7"/>
<cell id="8" material="1" universe="8"/>
<cell id="9" material="1" universe="9"/>
<cell id="10" fill="10" region="1 -2 3 -4" universe="11"/>
<lattice id="10">
<pitch>2.0 2.0</pitch>
<dimension>3 3</dimension>
<lower_left>-3.0 -3.0</lower_left>
<universes>
7 8 9
4 5 6
1 2 3 </universes>
</lattice>
<surface id="1" type="x-plane" boundary="vacuum" coeffs="-3.0"/>
<surface id="2" type="x-plane" boundary="vacuum" coeffs="3.0"/>
<surface id="3" type="y-plane" boundary="vacuum" coeffs="-3.0"/>
<surface id="4" type="y-plane" boundary="vacuum" coeffs="3.0"/>
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source type="independent" strength="1.0" particle="neutron">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<constraints>
<fissionable>true</fissionable>
</constraints>
</source>
</settings>
<tallies>
<filter id="1" type="surface">
<bins>1 2 3 4</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>current</scores>
</tally>
</tallies>
</model>Environment
Linux/gcc + macos/clang both seg fault
Reactions are currently unavailable