OpenMC Monte Carlo Code

Geant4 toolkit for the simulation of the passage of particles through matter - NIM A 506 (2003) 250-303

MC/DC: Monte Carlo Dynamic Code

Method of Characteristics neutral particle transport code for reactor physics written in Julia.

High performance cyclic ray tracing algorithm for neutron transport in Julia.

THOR is a radiation transport code for unstructured meshes.

An unstructured mesh library for automated method of characteristic mesh generation

One Dimensional Neutron Transport Solver

Energy-dependent neutron transport Monte Carlo implemented in Rust.

A neutron transport mini-app with both diamond-difference and linear-discontinuous finite element spatial discretisation options

Isotropic Monte Carlo simulations examining thermal neutron statistics in water, lead, and graphite, including animated neutron history, delta tracking and spherical geometry adaptations.

GEANT4 simulation code for LCS gamma-ray sources and flat efficiency moderated He-3 counters array dedicated to photoneutron reaction studies

This project aims to optimize the accuracy of critical size estimations by understanding and minimizing statistical fluctuations and transient effects. Once an optimal strategy is devised, the focus shifts to implementing a cylindrical geometry with a height equal to the radius and using the Monte Carlo code to estimate the critical length.

clone of diamond difference method configured to run with response matrix method for extended domains

Backwards raytracing simulator for polarized neutron imagers.

Implementation of the Ronen Method in 1D geometries