🌐 Power ocean cleanup and energy production with the CSG, a safe fusion-fission hybrid reactor designed for environmental restoration and waste transmutation.

GenNJOY is an open-source Python framework designed to automate the generation of high-fidelity, continuous-energy nuclear data libraries. It serves as a robust interface between raw Evaluated Nuclear Data Files (ENDF-6 format) and the NJOY2016 nuclear data processing system, streamlining the creation of ACE and HDF5 libraries for Monte Carlo codes

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).

Deterministic 2-group neutron diffusion solver for reactor core analysis

Core Design Assignments (PARCS)

Open technical release of the Cognitive Supernova Generator (CSG) fusion‑fission hybrid reactor: OpenMC neutronics model, materials, safety, and Peaceful Use–only license for ocean cleanup, waste transmutation, and humanitarian energy.

FREDS is a Python framework for multi-objective optimization of energy grid discretizations in reactor neutronics calculations. It uses sensitivity profiles generated with Serpent2 to guide the allocation of energy groups, enabling users to balance accuracy and computational efficiency in a principled way.

A Python toolkit for analyzing and visualizing neutron flux distributions. This tool provides utilities for processing neutron flux data, generating plots, and performing related nuclear physics calculations.

Neutron transport solver using collision probability method

A suite of parsers designed to make interacting with SERPENT output files simple and flawless

DRAGON V5 reactor physics code workshop with useful scripts and examples

High performance cyclic ray tracing algorithm for neutron transport in Julia.

Unity DOTS/ECS nuclear reactor simulator with real-time neutron physics, fission modeling, and RBMK positive void coefficient dynamics.

Open Nuclear Reactor Simulator

Fission Reactor Physics Homeworks

Machine Learning model used for the prediction of nuclear pressure vessel Embrittlement in advanced nuclear reactor , trained on 5000 unit USCB dataset of multiple US Nuclear reactors . Giving a MAE rate of 5% and r^2 accuracy score of 97% and Built upon latest Neural Network Architecture

Some code for my Physics of Fission Reactors model analysis reports, written in MATLAB and Python

Method of Characteristics neutral particle transport code for reactor physics written in Julia.

An open source nodal solver for nuclear reactors.

Open source Bateman Solver based on LSODE