Pinned Repositories
2017-MSRE-paper
Models and tools related to our 2017 MSRE dynamic modeling paper
aurora
Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
awesome-nuclear
A curated list of open source projects used in nuclear science and engineering
build123d
A python CAD programming library
cad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
cad_to_h5m
Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API
CAD_to_openMC
code to target the conversion from a step-file to a h5m-geometry for neutronics
cardinal
High-Resolution Nuclear Reactor Multiphysics
Chinese-STD-GB-T-7714-related-csl
GB/T 7714相关的csl以及Zotero使用技巧及教程。
FigureBestv4.4
FigureBestv4.4 SCI绘图美化
OpenMCNP's Repositories
OpenMCNP/FigureBestv4.4
FigureBestv4.4 SCI绘图美化
OpenMCNP/aurora
Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
OpenMCNP/awesome-nuclear
A curated list of open source projects used in nuclear science and engineering
OpenMCNP/build123d
A python CAD programming library
OpenMCNP/cad_to_dagmc
Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files
OpenMCNP/cad_to_h5m
Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API
OpenMCNP/CAD_to_openMC
code to target the conversion from a step-file to a h5m-geometry for neutronics
OpenMCNP/cardinal
High-Resolution Nuclear Reactor Multiphysics
OpenMCNP/Chinese-STD-GB-T-7714-related-csl
GB/T 7714相关的csl以及Zotero使用技巧及教程。
OpenMCNP/Cubit-plugin
Plugins and command extensions for Coreform Cubit
OpenMCNP/dataexplorer_v2
dataexplorer version 2
OpenMCNP/enrico
ENRICO: Exascale Nuclear Reactor Investigative COde
OpenMCNP/FluidX3D
The fastest and most memory efficient lattice Boltzmann CFD software, running on all GPUs via OpenCL.
OpenMCNP/GEOUNED
Current version of the code
OpenMCNP/IAMR
A parallel, adaptive mesh refinement (AMR) code that solves the variable-density incompressible Navier-Stokes equations.
OpenMCNP/libmesh
libMesh github repository
OpenMCNP/lshort-zh-cn
A Chinese edition of the Not So Short Introduction to LaTeX2ε
OpenMCNP/macaw
MaCaw is a MOOSE-based application that enables domain-decomposed neutral particle transport calculations in MOOSE. It leverages the ray tracing MOOSE module for unstructured mesh tracking and OpenMC for collision physics, handling material definitions, and tallying quantities.
OpenMCNP/moltres
Repository for Moltres, a code for simulating Molten Salt Reactors
OpenMCNP/moose
Multiphysics Object Oriented Simulation Environment
OpenMCNP/MSRE
OpenMCNP/MSRE_ARE_Models
OpenMCNP/msre_docker
OpenMCNP/neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
OpenMCNP/ONIX
ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers coupling with the open-source transport code OpenMC.
OpenMCNP/openmc
OpenMC Monte Carlo Code
OpenMCNP/openmc_plot
A Python package that plots OpenMC geometry using web based technologies
OpenMCNP/saltproc
Online reprocessing for molten salt reactors
OpenMCNP/stellarmesh
Create DAGMC geometry from CAD
OpenMCNP/watts
Workflow and Template Toolkit for Simulation (WATTS)