High-fidelity, benchmarked and validated OpenMC model of the University of Florida Training Reactor (UFTR)

Cascaide Software Infrastructure

Performance benchmarking of OpenMC

Simplified Stellarator CAD models.

From-scratch C++ and Python reimplementation of the Variational Moments Equilibrium Code (VMEC).

Project repository for "An Open Source Nuclear Modeling Ecosystem to Support Fusion Pilot Plant Design" collaboration between MIT and ANL

Python object generator for MOOSE codes

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

Automated V&V for fusion relevant CAD-based benchmarks

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 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.

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