Open Nuclear Reactor Simulator
A suite of parsers designed to make interacting with SERPENT output files simple and flawless
Method of Characteristics neutral particle transport code for reactor physics written in Julia.
An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
High performance cyclic ray tracing algorithm for neutron transport in Julia.
基于一阶泰勒展开的点堆中子动力学方程求解程序
DRAGON V5 reactor physics code workshop with useful scripts and examples
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).
Open source Bateman Solver based on LSODE
An open source nodal solver for nuclear reactors.
Neutron transport solver using collision probability method
Some code for my Physics of Fission Reactors model analysis reports, written in MATLAB and Python
Python scripts for Spent Nuclear Fuel Analysis, using SCALE/TRITON output files.
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.
Unity DOTS/ECS nuclear reactor simulator with real-time neutron physics, fission modeling, and RBMK positive void coefficient dynamics.
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.
Fission Reactor Physics Homeworks
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.
Wrapper script to determine the optimal reflector thickness for the MSR project
This repository contains the presentation I delivered to my nuclear engineer colleagues
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