openmc-dev/openmc

OpenMC Monte Carlo Code

Language: Python - Size: 70.7 MB - Last synced at: about 11 hours ago - Pushed at: about 13 hours ago - Stars: 846 - Forks: 543

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

Language: Jupyter Notebook - Size: 332 MB - Last synced at: about 2 months ago - Pushed at: about 2 months ago - Stars: 141 - Forks: 58

stellarmesh/stellarmesh

Meshing library for nuclear workflows

Language: Python - Size: 3.2 MB - Last synced at: 17 days ago - Pushed at: about 2 months ago - Stars: 49 - Forks: 11

idaholab/MontePy

MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

Language: Python - Size: 4.47 MB - Last synced at: about 14 hours ago - Pushed at: about 15 hours ago - Stars: 46 - Forks: 13

CambridgeNuclear/SCONE

Stochastic Calculator Of Neutron transport Equation

Language: Fortran - Size: 34 MB - Last synced at: 19 days ago - Pushed at: 19 days ago - Stars: 43 - Forks: 25

CEMeNT-PSAAP/MCDC

MC/DC: Monte Carlo Dynamic Code

Language: Python - Size: 20.9 MB - Last synced at: 3 days ago - Pushed at: about 1 month ago - Stars: 41 - Forks: 25

ukaea/paramak

Create parametric 3D fusion reactor CAD models

Size: 5.99 MB - Last synced at: 12 months ago - Pushed at: over 3 years ago - Stars: 36 - Forks: 12

fusion-energy/cad_to_dagmc

Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files

Language: Python - Size: 4.91 MB - Last synced at: 28 days ago - Pushed at: 29 days ago - Stars: 31 - Forks: 10

openmc-dev/openmc-ecosystem

List of open source projects related to OpenMC

Size: 13.7 KB - Last synced at: 9 months ago - Pushed at: 9 months ago - Stars: 19 - Forks: 9

ERMETE-Lab/MP-OFELIA

Openmc-FEnicsx for muLtiphysics tutorIAl

Language: Jupyter Notebook - Size: 18.5 MB - Last synced at: about 19 hours ago - Pushed at: about 20 hours ago - Stars: 16 - Forks: 5

NCSU-NCSG/THOR

THOR is a radiation transport code for unstructured meshes.

Language: Fortran - Size: 50 MB - Last synced at: about 2 months ago - Pushed at: 8 months ago - Stars: 13 - Forks: 6

fusion-energy/openmc_regular_mesh_plotter

A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.

Language: Python - Size: 183 KB - Last synced at: 22 days ago - Pushed at: 22 days ago - Stars: 11 - Forks: 1

fusion-energy/fusion_neutronics_workflow

Combines open source packages to produce an automated fusion specific neutronics workflow

Language: Python - Size: 1.39 MB - Last synced at: about 2 years ago - Pushed at: almost 3 years ago - Stars: 11 - Forks: 3

ukaea/SpaceClaim_API_NeutronicsTools

Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis

Language: C# - Size: 1.14 MB - Last synced at: about 2 years ago - Pushed at: about 4 years ago - Stars: 10 - Forks: 4

ENEA-Fusion-Neutronics/MCNP-Input-Reader

The package for reading mcnp input in a pythonic way

Language: Python - Size: 190 KB - Last synced at: about 12 hours ago - Pushed at: almost 3 years ago - Stars: 8 - Forks: 4

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.

Language: Python - Size: 512 KB - Last synced at: almost 2 years ago - Pushed at: almost 2 years ago - Stars: 7 - Forks: 2

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

Language: Python - Size: 41 KB - Last synced at: about 1 month ago - Pushed at: over 2 years ago - Stars: 7 - Forks: 3

terrapower/armicontrib-dif3d

DIF3D plugin to the ARMI nuclear reactor analysis framework

Language: Python - Size: 2.57 MB - Last synced at: over 1 year ago - Pushed at: almost 3 years ago - Stars: 7 - Forks: 3

open-radiation-sources/parametric-plasma-source

Language: C++ - Size: 280 KB - Last synced at: over 2 years ago - Pushed at: over 2 years ago - Stars: 6 - Forks: 4

egor1abs/openmc_sdef_parser

MCNP SDEF to OpenMC conversion tool

Language: Python - Size: 146 KB - Last synced at: about 1 month ago - Pushed at: about 1 month ago - Stars: 5 - Forks: 0

fusion-energy/model_benchmark_zoo

A collection of neutronics models for comparing neutronics simulations in both CAD and CSG formats.

Language: Python - Size: 331 KB - Last synced at: about 1 year ago - Pushed at: about 1 year ago - Stars: 5 - Forks: 3

fusion-energy/spectrum_plotter

A Python package for creating publication quality plots for neutron / photon / particle spectrum

Language: Python - Size: 96.7 KB - Last synced at: 1 day ago - Pushed at: about 3 years ago - Stars: 4 - Forks: 1

nfherrin/OpenXSConverter

An open source utility to convert various publicly available macroscopic nuclear cross section formats

Language: Fortran - Size: 108 KB - Last synced at: 10 months ago - Pushed at: 10 months ago - Stars: 3 - Forks: 2

tumregels/asciiviewer

A pretty viewer for XSM files generated by DRAGON/DONJON or APOLLO neutronic codes

Language: Python - Size: 9.21 MB - Last synced at: almost 2 years ago - Pushed at: about 2 years ago - Stars: 3 - Forks: 3

fusion-energy/vertices_to_h5m

Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations

Language: Python - Size: 411 KB - Last synced at: 9 days ago - Pushed at: about 2 years ago - Stars: 3 - Forks: 2

openmc-data-storage/material_xs_plotter

XSPlot - Neutron cross section plotter for materials

Language: Python - Size: 82 KB - Last synced at: about 1 month ago - Pushed at: about 2 years ago - Stars: 3 - Forks: 3

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.

Language: Python - Size: 64.5 KB - Last synced at: 19 days ago - Pushed at: over 2 years ago - Stars: 3 - Forks: 2

ZXG818/CylinderMeshingTool

A high-fidelity, free user input cylinder meshing tool for MCNP.

Language: C - Size: 412 KB - Last synced at: over 1 year ago - Pushed at: almost 4 years ago - Stars: 3 - Forks: 0

NielsBongers/neutron-transport-monte-carlo

Energy-dependent neutron transport Monte Carlo implemented in Rust.

Language: Rust - Size: 7.83 MB - Last synced at: 7 months ago - Pushed at: 7 months ago - Stars: 2 - Forks: 0

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.

Language: Jupyter Notebook - Size: 14.5 MB - Last synced at: 2 months ago - Pushed at: almost 2 years ago - Stars: 2 - Forks: 0

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.

Language: Rust - Size: 5.84 MB - Last synced at: 6 months ago - Pushed at: 6 months ago - Stars: 1 - Forks: 0

myerspat/ttnte

Tensor Trains (TTs) applied to the Neutron Transport Equation (NTE).

Language: HTML - Size: 94.8 MB - Last synced at: 4 days ago - Pushed at: 4 days ago - Stars: 0 - Forks: 0

etare8/neutronic-openmc-stuff

Neutronics using OpenMC Monte Carlo Code

Language: Jupyter Notebook - Size: 853 KB - Last synced at: 7 months ago - Pushed at: 7 months ago - Stars: 0 - Forks: 0

fusion-energy/fusion-neutronics-presentation-slides

An open source slide deck on fusion neutronics

Language: HTML - Size: 21.6 MB - Last synced at: about 2 months ago - Pushed at: 7 months ago - Stars: 0 - Forks: 0

etare8/fission-reactor-physics

Fission Reactor Physics Homeworks

Language: Jupyter Notebook - Size: 2.6 MB - Last synced at: 7 months ago - Pushed at: 7 months ago - Stars: 0 - Forks: 0

fusion-energy/brep_part_finder

A Python package to identify the part ID number in Brep format CAD files

Language: Python - Size: 157 KB - Last synced at: 8 days ago - Pushed at: over 2 years ago - Stars: 0 - Forks: 0

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

Language: Python - Size: 32.2 KB - Last synced at: 12 months ago - Pushed at: about 3 years ago - Stars: 0 - Forks: 0