OpenMC Monte Carlo Code
Main yt repository
A curated list of open source projects used in nuclear science and engineering
Open Nuclear Reactor 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.
The main whatisnuclear.com website
List of open source projects related to OpenMC
An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
Format description for ACE nuclear data files
Online reprocessing for molten salt reactors
Papillon Nuclear Data Library
THOR is a radiation transport code for unstructured meshes.
Python Framework for data-driven model Order Reduction of multi-physiCs problEms
Holds the research group website.
The sciantix-official repository contains the SCIANTIX code for fission gas behaviour, together with the validation database and regression files.
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).
Package Manager for Nuclear Engineering Development
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