OpenMOC is a Method of Characteristics neutral particle transport code for reactor physics criticality calculations. It is capable of simulating 2D models based on constructive solid geometry with second-order surfaces. High performance parallel solvers for multi-core, many-core and GPUs are actively pursued as part of the OpenMOC project.
This is an example of a full core transport using OpenMOC on Rescale.
|Simulation Code||OpenMOC 0.1.2|
|Analysis Type||Monte Carlo particle transport simulation|
|Description||An example of a full core transport.|
|Suggested Hardware||Titanium / 2 cores|
python full-core.py --num-omp-threads=2 -i 50
|Estimated Run Time||23 minutes|