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.
Fission Reactor Physics Homeworks
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.
Unity DOTS/ECS nuclear reactor simulator with real-time neutron physics, fission modeling, and RBMK positive void coefficient dynamics.
Wrapper script to determine the optimal reflector thickness for the MSR project
Several modules with lessons of different aspects of reactor physics
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.
Monte Carlo simulation of neutron moderation. Reproduces spectral hardening and 1/v tail behavior based on Coveyou et al. (1956) . Validates the Wigner-Wilkins (1944) relationship (T_m/T_e) using C and Python. Features 1,000,000 histories and rejection sampling.
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
Deterministic 2-group neutron diffusion solver for reactor core analysis
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
Source code for Dragon/Donjon
🌐 Power ocean cleanup and energy production with the CSG, a safe fusion-fission hybrid reactor designed for environmental restoration and waste transmutation.
An open source nodal solver for nuclear reactors.
Open source Bateman Solver based on LSODE
Neutron transport solver using collision probability method
This repository contains the presentation I delivered to my nuclear engineer colleagues
Some code for my Physics of Fission Reactors model analysis reports, written in MATLAB and Python
High performance cyclic ray tracing algorithm for neutron transport in Julia.
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