OpenMC Monte Carlo Code
Main yt repository
A curated list of open source projects used in nuclear science and engineering
Open Nodal Core Simulator
A suite of parsers designed to make interacting with SERPENT output files simple and flawless
Tool for converting MCNP input files to OpenMC classes/XML
MC/DC: Monte Carlo Dynamic Code
A point kinetic reactor model with GUI frontend. Meant to be used as a demo for teaching K-12 students about nuclear engineering tech.
List of open source projects related to OpenMC
The main whatisnuclear.com website
An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
Online reprocessing for molten salt reactors
Format description for ACE nuclear data files
Code for reproducing the paper "GenCP: Towards Generative Modeling Paradigm of Coupled physics" (ICLR 2026: https://arxiv.org/abs/2601.19541).
Papillon Nuclear Data Library
Python Framework for data-driven model Order Reduction of multi-physiCs problEms
THOR is a radiation transport code for unstructured meshes.
The sciantix-official repository contains the SCIANTIX code for fission gas behaviour, together with the validation database and regression files.
Monte Carlo neutron transport in C99. GPU via Booth (AMD MI300X, NVIDIA RTX). ENDF/B-VII.1 nuclear data. Validated against ICSBEP benchmarks.
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).
To associate your repository with the nuclear-engineering topic, visit your repo's landing page and select "manage topics."