reactor-physics

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.

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

Python reference implementation for finite-volume neutron-diffusion calculations on regular hex-z lattices

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.

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

Deterministic 2-group neutron diffusion solver for reactor core analysis

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

Desktop GUI for building, previewing, running and analysing OpenMC reactor models — pin to full core, depletion, kinetics, V&V (TR/EN)

MMPA matrix-exponential solver for linear decay chains. Order 32 verified against Bateman and Radau.

Several modules with lessons of different aspects of reactor physics

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.

Open-source, continual-learning autonomous control system for advanced molten-salt microreactors — and, eventually, a reference design of one.

Six-group point kinetics with a stiff Radau integrator, verified against the inhour equation and prompt-jump approximation

Monte Carlo neutron transport in OpenMC over a PWR pin-cell lattice, with a Gaussian-process surrogate for k-infinity measured against the stochastic uncertainty of the calculation it replaces. Reactivity coefficients validated against transport runs the surrogate never saw.

Nuclear reactor simulator including point kinetics, diffusion and thermal-hydraulics solvers.