Geant4 vs XCOM photon cross section comparison and plotting

Multi-tally (mesh + energy) simulation, analysis and visualization of neutron spectrum variations in a PWR fuel pin model using OpenMC.

A PyQt5-based GUI application to visualize Serpent Monte Carlo reactor simulation results using Octave scripts. Supports plotting burnup-dependent nuclide densities, neutron flux spectra, and keff …

A GUI-based internal dose calculator using ICRP phantoms and S-value datasets. Supports adult male and female models for I-131, Lu-177, and Ra-223.

Compare ENDF nuclear data processed by NJOY and FRENDY into ACE format with visual cross-section analysis.

Neutron diffusion-Gaussian-Cartesian-2D-3D

A Python tool that reads isotope data from a JSON file and generates Serpent-compatible material definitions for fuel mixtures including uranium, gadolinium, and oxygen isotopes.

A sequence of Jupyter notebooks featuring the "12 Steps to Navier-Stokes" http://lorenabarba.com/