Open Nodal Core Simulator
A suite of parsers designed to make interacting with SERPENT output files simple and flawless
Deterministic real-time emulation framework for flowing-fuel MSRE transients with delayed core/BOP coupling and FPGA-oriented split-kernel execution.
An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
Method of Characteristics neutral particle transport code for reactor physics written in Julia.
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
Unity DOTS/ECS nuclear reactor simulator with real-time neutron physics, fission modeling, and RBMK positive void coefficient dynamics.
Open source Bateman Solver based on LSODE
Some code for my Physics of Fission Reactors model analysis reports, written in MATLAB and Python
Neutron transport solver using collision probability method
An open source nodal solver for nuclear reactors.
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.
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
Six-group point reactor kinetics solver in python, verified against the Inhour equation and Prompt Jump Approximation
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