Topic: neutronics Goto Github
Some thing interesting about neutronics
Some thing interesting about neutronics
neutronics,Stochastic Calculator Of Neutron transport Equation
Organization: cambridgenuclear
Home Page: https://scone.readthedocs.io
neutronics,MC/DC: Monte Carlo Dynamic Code
Organization: cement-psaap
Home Page: https://mcdc.readthedocs.io/en/latest/
neutronics,The package for reading mcnp input in a pythonic way
Organization: enea-fusion-neutronics
neutronics,Openmc-FEnicsx for muLtiphysics tutorIAl
Organization: ermete-lab
Home Page: https://ermete-lab.github.io/MP-OFELIA/intro.html
neutronics,A Python package to identify the part ID number in Brep format CAD files
Organization: fusion-energy
neutronics,Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
Organization: fusion-energy
neutronics,An open source slide deck on fusion neutronics
Organization: fusion-energy
neutronics,Combines open source packages to produce an automated fusion specific neutronics workflow
Organization: fusion-energy
neutronics,A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC
Organization: fusion-energy
neutronics,A collection of neutronics models for comparing neutronics simulations in both CAD and CSG formats.
Organization: fusion-energy
neutronics,A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
Organization: fusion-energy
neutronics,A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.
Organization: fusion-energy
Home Page: https://openmc-dagmc-wrapper.readthedocs.io/
neutronics,A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
Organization: fusion-energy
neutronics,A Python package for creating publication quality plots for neutron / photon / particle spectrum
Organization: fusion-energy
neutronics,Convert non overlapping STL files into a DAGMC h5m file complete with material tags and ready for use in neutronics simulations.
Organization: fusion-energy
neutronics,Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations
Organization: fusion-energy
neutronics,MontePy is a Python library (API) to read, edit, and write MCNP input files.
Organization: idaholab
Home Page: https://www.montepy.org/
neutronics,THOR is a radiation transport code for unstructured meshes.
Organization: ncsu-ncsg
neutronics,An open source utility to convert various publicly available macroscopic nuclear cross section formats
User: nfherrin
neutronics,Energy-dependent neutron transport Monte Carlo implemented in Rust.
User: nielsbongers
Home Page: https://nielsbongers.github.io/docs/nuclear/nuclear/index.html
neutronics,
Organization: open-radiation-sources
neutronics,XSPlot - Neutron cross section plotter for materials
Organization: openmc-data-storage
neutronics,OpenMC Monte Carlo Code
Organization: openmc-dev
Home Page: https://docs.openmc.org
neutronics,List of open source projects related to OpenMC
Organization: openmc-dev
neutronics,Isotropic Monte Carlo simulations examining thermal neutron statistics in water, lead, and graphite, including animated neutron history, delta tracking and spherical geometry adaptations.
User: patrikasvanagas
neutronics,Command line tool to convert MCNP mesh tallies to Visual ToolKit (VTK) formats. Supports all MCNPv6.2 legacy meshtal output formats, for both for rectangular and cylindrical meshes.
User: repositony
neutronics,A modular toolkit of fast and reliable libraries for neutronics analysis. Several command line tools are built with this core collection of crates.
User: repositony
Home Page: https://repositony.github.io/ntools/
neutronics,Simple code to simulate Neutron Scattering in Non-Radiative matter using Monte Carlo simulations
User: sg2405
neutronics,The same neutronics geometry made using Constructive Solid Geometry (CSG) and DAGMC faceteted surface mesh at different resolutions to compare simulation results
User: shimwell
neutronics,Meshing library for nuclear workflows
Organization: stellarmesh
neutronics,DIF3D plugin to the ARMI nuclear reactor analysis framework
Organization: terrapower
Home Page: https://terrapower.github.io/armicontrib-dif3d/
neutronics,A pretty viewer for XSM files generated by DRAGON/DONJON or APOLLO neutronic codes
User: tumregels
neutronics,Create parametric 3D fusion reactor CAD models
Organization: ukaea
Home Page: https://paramak.readthedocs.io/en/main/
neutronics,Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
Organization: ukaea
neutronics,A high-fidelity, free user input cylinder meshing tool for MCNP.
User: zxg818
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