OpenMC Monte Carlo Code

A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools

Create parametric 3D fusion reactor CAD and neutronics models

ENRICO: Exascale Nuclear Reactor Investigative COde

Native plotting GUI for model design and verification

Meshing library for nuclear workflows

Tool for converting MCNP input files to OpenMC classes/XML

Creates a plasma source as an openmc.source object from input parameters that describe the plasma

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

Workflow and Template Toolkit for Simulation (WATTS)

List of open source projects related to OpenMC

A tool for making reproducible materials and standardizing use across several neutronics codes

A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak

Openmc-FEnicsx for muLtiphysics tutorIAl

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

A Python package for downloading h5 cross section files for use in OpenMC.

A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles

Package Manager for Nuclear Engineering Development

A Genetic Algorithm (GA) / Discrete Particle Swarm Optimization/ Hybrid (GA-PSO) for nuclear fuel optimization using ML surrogates (DNN, KNN, Random Forest, Ridge) and OpenMC. Optimizes fuel loading patterns for a target k-eff and minimal Power Peaking Factor (PPF).

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