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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.


Import Job Setup Get Job Results


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
Command
mpirun -f $HOME/mpd.hosts -n 2 -ppn 1 openmc -s 8 $(pwd)
Estimated Run Time 1 minute

Last Updated: Apr 26, 2017 11:31AM PDT

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