OpenMC Monte Carlo Code

Geant4 toolkit for the simulation of the passage of particles through matter - NIM A 506 (2003) 250-303

A curated list of open source projects used in nuclear science and engineering

Celeritas is a new Monte Carlo transport code designed to accelerate scientific discovery in high energy physics by improving detector simulation throughput and energy efficiency using GPUs.

ENRICO: Exascale Nuclear Reactor Investigative COde

Native plotting GUI for model design and verification

For shallow-water Lagrangian particle routing.

MC/DC: Monte Carlo Dynamic Code

Monte Carlo Simulation propagating charged Leptons through Media as C++ Library

THOR is a radiation transport code for unstructured meshes.

Two phase particle transport model simulating formation damage in porous media

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

Energy-dependent neutron transport Monte Carlo implemented in Rust.

This repository contains a beginner-friendly tutorial for OpenMC, a Monte Carlo particle transport simulation code widely used in nuclear engineering.

(M)onte Carlo (I)nteraction and (D)osimetry (S)imulation of (X)-Rays. WIP senior thesis project at Saint Vincent College.

DECIMA (Data Extraction & Contextual Inference for MCNP Analysis) — MCNP PTRAC parsing, advanced analysis, and contextual inference tool combining a nuclear physics knowledge graph and an LLM-powered assistant to deliver accurate, no-code answers for neutron and photon transport simulations, built on the official MCNPTools library from LANL.

High-performance hybrid (C++/Python) Monte Carlo engine for Gamma Spectroscopy. Built from first principles to simulate photon transport, analytical ray-tracing geometry, and validate backscatter phenomena against experimental data.