neutronics
There are 36 repositories under neutronics topic.
openmc-dev/openmc
OpenMC Monte Carlo Code
fusion-energy/neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
stellarmesh/stellarmesh
Meshing library for nuclear workflows
ukaea/paramak
Create parametric 3D fusion reactor CAD models
CambridgeNuclear/SCONE
Stochastic Calculator Of Neutron transport Equation
idaholab/MontePy
MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
CEMeNT-PSAAP/MCDC
MC/DC: Monte Carlo Dynamic Code
fusion-energy/cad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
openmc-dev/openmc-ecosystem
List of open source projects related to OpenMC
fusion-energy/fusion_neutronics_workflow
Combines open source packages to produce an automated fusion specific neutronics workflow
ukaea/SpaceClaim_API_NeutronicsTools
Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
NCSU-NCSG/THOR
THOR is a radiation transport code for unstructured meshes.
ERMETE-Lab/MP-OFELIA
Openmc-FEnicsx for muLtiphysics tutorIAl
fusion-energy/model_benchmark_zoo
A collection of neutronics models for comparing neutronics simulations in both CAD and CSG formats.
fusion-energy/openmc_regular_mesh_plotter
A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
ENEA-Fusion-Neutronics/MCNP-Input-Reader
The package for reading mcnp input in a pythonic way
fusion-energy/openmc-dagmc-wrapper
A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.
terrapower/armicontrib-dif3d
DIF3D plugin to the ARMI nuclear reactor analysis framework
fusion-energy/inertial_fusion_openmc_dagmc_paramak_example
A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC
fusion-energy/spectrum_plotter
A Python package for creating publication quality plots for neutron / photon / particle spectrum
fusion-energy/stl_to_h5m
Convert non overlapping STL files into a DAGMC h5m file complete with material tags and ready for use in neutronics simulations.
fusion-energy/vertices_to_h5m
Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations
nfherrin/OpenXSConverter
An open source utility to convert various publicly available macroscopic nuclear cross section formats
openmc-data-storage/material_xs_plotter
XSPlot - Neutron cross section plotter for materials
tumregels/asciiviewer
A pretty viewer for XSM files generated by DRAGON/DONJON or APOLLO neutronic codes
ZXG818/CylinderMeshingTool
A high-fidelity, free user input cylinder meshing tool for MCNP.
NielsBongers/neutron-transport-monte-carlo
Energy-dependent neutron transport Monte Carlo implemented in Rust.
patrikasvanagas/MC-Thermal-Neutron-Transport
Isotropic Monte Carlo simulations examining thermal neutron statistics in water, lead, and graphite, including animated neutron history, delta tracking and spherical geometry adaptations.
repositony/mesh2vtk
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.
repositony/ntools
A modular toolkit of fast and reliable libraries for neutronics analysis. Several command line tools are built with this core collection of crates.
sg2405/Neutronics_MonteCarlo
Simple code to simulate Neutron Scattering in Non-Radiative matter using Monte Carlo simulations
fusion-energy/brep_part_finder
A Python package to identify the part ID number in Brep format CAD files
fusion-energy/fusion-neutronics-presentation-slides
An open source slide deck on fusion neutronics
gglemp/Simulations-of-the-point-reactor-dynamics-of-AP1000-using-MATLAB-environment
Intermediate project about Point Kintetics and Dynamics Equations simulation of AP1000 reactor
shimwell/neutronics_geomentry_comparision_simulation
The same neutronics geometry made using Constructive Solid Geometry (CSG) and DAGMC faceteted surface mesh at different resolutions to compare simulation results