OpenMC Example

OpenMC is a Monte Carlo code used for neutron criticality computations in particle transport simulations. It simulates 3D models based on constructive solid geometry with second-order surfaces.

This example is a hybrid example job from the test suite using OpenMC and MPICH.

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Simulation Code OpenMC 0.6.0
Analysis Type Monte Carlo particle transport simulation
Description An example based on the test "test_source_energy_maxwell".
Suggested Hardware Titanium / 20 cores
mpirun -f $HOME/mpd.hosts -n 2 -ppn 1 openmc -s 8 $(pwd)
Estimated Run Time 1 minute