Add to ORKGThe present work describes the latest advances and progress in the development of the OpenMC Monte Carlo code, an open-source code originating from the Massachusetts Institute of Technology. First, an overview of the development workflow of OpenMC is given. Various enhancements to the code such as real-time XML input validation, state points, plotting, OpenMP threading, and coarse mesh finite difference acceleration are described.United States. Department of Energy. Naval Reactors Division (Rickover Fellowship Program in Nuclear Engineering)United States. Department of Energy (Consortium for Advanced Simulation of Light Water Reactors. Contract DE-AC05-00OR22725)United States. Department of Energy. Office of Advanced Scientific Computing R...
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This work describes newly developed features of the OpenMC code for nuclear data processing. OpenMC,...
This release of OpenMC adds several major new features: depletion, photon transport, and support for...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently ...
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute o...
This release of OpenMC includes an assortment of new features and many bug fixes. In particular, the...
This release of OpenMC includes several new features, performance improvements, and bug fixes compar...
This release of OpenMC includes many bug fixes, performance improvements, and several notable new fe...
This release of OpenMC includes many bug fixes as well as improvements in geometry modeling, mesh fu...
This release of OpenMC is the first release to use a new native HDF5 cross section format rather tha...
This release of OpenMC includes a few new major features including the capability to perform neutron...
Performance results are presented for a multi-threaded version of the OpenMC Monte Carlo neutronics ...
This release of OpenMC provides some substantial improvements over version 0.7.0. Non-simple cell re...
This release of OpenMC includes an assortment of new features and many bug fixes. The openmc.deplete...
This release of OpenMC includes several bug fixes, performance improvements for complex geometries a...
This work describes newly developed features of the OpenMC code for nuclear data processing. OpenMC,...
This release of OpenMC adds several major new features: depletion, photon transport, and support for...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
This paper gives an overview of OpenMC, an open source Monte Carlo particle transport code recently ...
A new Monte Carlo code called OpenMC is currently under development at the Massachusetts Institute o...
This release of OpenMC includes an assortment of new features and many bug fixes. In particular, the...
This release of OpenMC includes several new features, performance improvements, and bug fixes compar...
This release of OpenMC includes many bug fixes, performance improvements, and several notable new fe...
This release of OpenMC includes many bug fixes as well as improvements in geometry modeling, mesh fu...
This release of OpenMC is the first release to use a new native HDF5 cross section format rather tha...
This release of OpenMC includes a few new major features including the capability to perform neutron...
Performance results are presented for a multi-threaded version of the OpenMC Monte Carlo neutronics ...
This release of OpenMC provides some substantial improvements over version 0.7.0. Non-simple cell re...
This release of OpenMC includes an assortment of new features and many bug fixes. The openmc.deplete...
This release of OpenMC includes several bug fixes, performance improvements for complex geometries a...
This work describes newly developed features of the OpenMC code for nuclear data processing. OpenMC,...
This release of OpenMC adds several major new features: depletion, photon transport, and support for...
An algorithm for decomposing large tally data in Monte Carlo particle transport simulations is devel...
