reactor-physics

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

Open Nodal Core Simulator

An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool

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

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

Deterministic real-time emulation framework for flowing-fuel MSRE transients with delayed core/BOP coupling and FPGA-oriented split-kernel execution.

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).

Multigroup neutron diffusion in 1-D and 2-D (structured and unstructured), with k-eigenvalue, fixed-source and kinetics solvers. C++ core, Python bindings.

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

Neutron transport solver using collision probability method

Python scripts for Spent Nuclear Fuel Analysis, using SCALE/TRITON output files.

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

This repository contains the presentation I delivered to my nuclear engineer colleagues

Neutronics Analysis to Optimise Neutron Shielding Materials in Spherical Tokamak Using OpenMC.

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

Interactive browser-based 1D reactor-channel thermal-hydraulic solver with steam-table properties and engineering visualization.

Source code for Dragon/Donjon

Pure-Rust continuous-energy Monte Carlo radiation transport: neutron k-eigenvalue, photon, coupled n-γ heating, CRAM depletion, point kinetics, CE adjoint. CPU + cross-vendor GPU (CUDA/ROCm/Vulkan/Metal via CubeCL). Reads OpenMC HDF5 directly. Grew out of an SVD cross-section compression study.

An open source nodal solver for nuclear reactors.