OpenMC is a community-developed Monte Carlo neutron and photon transport simulation code. It is capable of performing fixed source, k-eigenvalue, and subcritical multiplication calculations on models built using either a constructive solid geometry or CAD representation. OpenMC supports both continuous-energy and multigroup transport. The continuous-energy particle interaction data is based on a native HDF5 format that can be generated from ACE files produced by NJOY. Parallelism is enabled via a hybrid MPI and OpenMP programming model.
More information about the OpenMC Monte Carlo Code.
During the course, participants will have access to a pre-installed version of OpenMC on cloud-based servers.
The OpenMC course will be taught in English during the week of 25-28 April 2022 from 10:00-14:00 (CDT time)/17:00-21:00 (CEST time).
Maximum number of participants: 30
For any questions about this course, please reach out to Ms. Hedvig Nahon (firstname.lastname@example.org).