MC-10 spent-fuel dry storage cask muon scattering simulation datasets

The MC-10 spent-fuel dry storage cask muon scattering dataset was generated through Geant4-based Monte Carlo simulations to support research on muon imaging and reconstruction algorithms for nuclear material monitoring. The dataset provides detailed muon transport and scattering information as muons pass through a full-scale MC-10 spent-fuel DSC model.The simulation incorporated realistic material compositions—including uranium dioxide (UO₂) fuel assemblies, carbon steel cask structures, and concrete shielding—with a total height of 386.2 cm for the fuel assembly layer. Each muon event includes incident and exiting track parameters, scattering angles, and hit coordinates across multiple detector planes.This dataset is primarily designed for validating and benchmarking muon scattering tomography (MST). It enables performance evaluation under various flux and noise conditions, providing a valuable resource for research in nuclear security, spent-fuel verification, and high-density material imaging.