spack.io : py-openmc : develop
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.
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purl: pkg:spack/py-openmc@develop
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- git *
- openmc *
- py-cython *
- py-h5py *
- py-ipython *
- py-lxml *
- py-matplotlib *
- py-mpi4py *
- py-numpy *
- py-pandas *
- py-pip *
- py-scipy *
- py-setuptools *
- py-uncertainties *
- py-wheel *
- python *