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conda-forge.org : openmc

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.

Registry - Source - Homepage - JSON
purl: pkg:conda/openmc
Keywords: computational-physics, high-performance-computing, monte-carlo-simulation, neutron-transport, neutronics, nuclear-data, nuclear-energy, nuclear-engineering, nuclear-fusion, openmc, particle-transport, photon-transport, radiation-transport
License: MIT
Latest release: over 1 year ago
First release: over 1 year ago
Dependent packages: 3
Dependent repositories: 1
Stars: 492 on GitHub
Forks: 359 on GitHub
See more repository details: repos.ecosyste.ms
Last synced: 7 days ago

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