Open Nodal Core Simulator

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

An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool

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.

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

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).

DRAGON V5 reactor physics code workshop with useful scripts and examples

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

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

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.

Deterministic 2-group neutron diffusion solver for reactor core analysis

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

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.