mirror of
https://git.FreeBSD.org/ports.git
synced 2025-01-16 07:58:04 +00:00
11 lines
569 B
Plaintext
11 lines
569 B
Plaintext
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.
|
|
|
|
WWW: https://openmc.org/
|