Python object generator for MOOSE codes

This is the GitHub repository for STELLOPT, the state-of-the-art stellarator optimization code.

Create OpenMC source definition from tabulated plasma parameters

code to target the conversion from a step-file to a h5m-geometry for neutronics

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

a CAD to MC geometry conversion tool

Direct Accelerated Geometry Monte Carlo Toolkit

Accelerated Discretized Geometry

An open-source nuclear reactor analysis automation framework that helps design teams increase efficiency and quality

ARMI plugin for building and running OpenMC models

Parametric 3-D CAD modeling toolset for stellarator fusion devices

Meshing library for nuclear workflows

A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB

A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes

List of open source projects related to OpenMC

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

our next generation fast and scalable CFD code

Python ENDF Parser

A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.

ENDF files of the FENDL library

A free, open-source Binary Collision Approximation (BCA) code for ion-material interactions including sputtering, implantation, and reflection

A python package for accessing various properties of elements, ions and isotopes in the periodic table of elements.

Fast Relaxed Vector Fitting Implementation in C

PyNjoy2016

Repository for FES Shutdown Dose Rate Workflows project

Stochastic Calculator Of Neutron transport Equation

MC/DC: Monte Carlo Dynamic Code