![]() Suitable for traditional and liquid-fuel reactors. ![]() It includes sub-solvers for neutronics (point kinetics, diffusion, SP3, SN), one- and two-phase thermal-hydraulics, and thermal-mechanics. Multiphysics solver based on OpenFOAM and dedicated to nuclear reactor safety analysis. OpenFOAM-based multi-dimensional solver for fuel behavior. General-purpose structure and thermal-mechanics analysis.įor material properties, various interfaces are also provided and covers the following languages C, C++, python, fortran, etc. Structural mechanics, Fuel behavior, Materials Name TRUST serves as a basis for various applications, TrioCFD being the most well-known one. fast-neutron reactor simulation, nuclear propulsion, but also now fuel cells simulations, chemistry, etc.). Its flexible, object-oriented architecture allows for the development of target-oriented applications (e.g. Open-source platform of fluid mechanics and thermohydraulics with massive parallel computing capabilities. Modular, object-oriented and allowing massive parallel computing, TrioCFD has a wide range of applications, from industrial applications to scientific research. CFD code for single and two-phase flows. It features an intuitive API that allows easily tailoring available solvers or creating new solvers. Open-source CFD solver based on the spectral element methodįinite-volume library with an extensive range of features to solve anything from complex fluid flows involving chemical reactions, turbulence and heat transfer, to acoustics, solid mechanics and electromagnetics. Large-eddy simulation (LES) code for low-speed flows, with an emphasis on smoke and heat transport from fires. To be published in late 2020, contact GPL OpenFOAM-based solver for containment studies in Light Water Reactors. Simulation of the generation, transport, evolution and deposition of multispecies aerosol mixtures. Thermal-hydraulics, system analysis, containment Nameīased on the OpenFOAM software package. Modern Monte Carlo code based on object-oriented programming and purpose-made for easily testing methods and algorithms. It is capable of simulating 2D assembly and full-core reactor models based on constructive solid geometry with second-order surfaces. Method of Characteristics (MOC) neutral particle transport code for reactor physics criticality calculations. ![]() It is a constructive solid geometry, continuous-energy transport code that uses HDF5 format cross sections. ![]() Would you be aware of other relevant software that could complement this list, please check the contribution guidelines (to be made available soon!) and contact us at Nameĭeterministic reactor physics platform including a lattice code, full-core flux solvers, and a full-core operation analysis tool.įully-featured Monte Carlo particle transport code. The authors acknowledge the fact that they might have overlooked on several available open-source codes. It does not include software that is not made available by its developers, nor software whose development has been discontinued. ![]() This preliminary list has been compiled by the ONCORE expert group. V/HTR safety analyses for the quantification of fission product release from the fuel. HTR pebble-type design and safety analysis Want to get involved? You are invited to submit code to be included in this list, please follow the instruction available at Get Involved?. Codes available through ONCORE Name ![]()
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