AbstractOpenMC is a new Monte Carlo transport particle simulation code focused on solving two types of neutronic problems mainly the k-eigenvalue criticality fission source problems and external fixed fission source problems. OpenMC does not have any Graphical User Interface and the creation of one is provided by our java-based application named ERSN-OpenMC. The main feature of this application is to provide to the users an easy-to-use and flexible graphical interface to build better and faster simulations, with less effort and great reliability. Additionally, this graphical tool was developed with several features, as the ability to automate the building process of OpenMC code and related libraries as well as the users are given the freedo...
Aims. We present r-Java 2.0, a nucleosynthesis code for open use that performs r-process calculation...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
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...
A new version of the code system PENGEOM, which provides a complete set of tools to handle different...
A code package consisting of the Monte Carlo Library MCLIB, the executing code MC{_}RUN, the web app...
A new version of the code system pengeom, which provides a complete set of tools to handle different...
The present work describes the latest advances and progress in the development of the OpenMC Monte C...
RunMC is an object-oriented framework aimed to generate and to analyse high-energy collisions of ele...
The program McCad provides a CAD interface for the Monte Carlo transport code MCNP. It is able to co...
AbstractOpenCL and OpenACC are generic frameworks for heterogeneous programming using CPU and accele...
This paper reviews the ecosystem of GATE, an open-source Monte Carlo toolkit for medical physics. Ba...
OpenCL and OpenACC are generic frameworks for heterogeneous programming using CPU and accelerator de...
International audienceThe OpenDose collaboration has been established to generate an open and tracea...
Aims. We present r-Java 2.0, a nucleosynthesis code for open use that performs r-process calculation...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
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...
A new version of the code system PENGEOM, which provides a complete set of tools to handle different...
A code package consisting of the Monte Carlo Library MCLIB, the executing code MC{_}RUN, the web app...
A new version of the code system pengeom, which provides a complete set of tools to handle different...
The present work describes the latest advances and progress in the development of the OpenMC Monte C...
RunMC is an object-oriented framework aimed to generate and to analyse high-energy collisions of ele...
The program McCad provides a CAD interface for the Monte Carlo transport code MCNP. It is able to co...
AbstractOpenCL and OpenACC are generic frameworks for heterogeneous programming using CPU and accele...
This paper reviews the ecosystem of GATE, an open-source Monte Carlo toolkit for medical physics. Ba...
OpenCL and OpenACC are generic frameworks for heterogeneous programming using CPU and accelerator de...
International audienceThe OpenDose collaboration has been established to generate an open and tracea...
Aims. We present r-Java 2.0, a nucleosynthesis code for open use that performs r-process calculation...
We have developed a multi-group Monte Carlo neutron transport code using C++ and the Parallel Object...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...