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

Energy-dependent neutron transport Monte Carlo implemented in Rust.

Unity DOTS/ECS nuclear reactor simulator with real-time neutron physics, fission modeling, and RBMK positive void coefficient dynamics.

Neutron transport solver using collision probability method

Solves the RTE using the MOC on tetraedral meshes

One Dimensional Neutron Transport Solver

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

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

SRT_repo is built when first learning how to perform the neutron transport calculating during an SRT in Tsinghua University. This repo is primitive but easy-taking for the new comer when you want to buld your COM program hand-by-hand.

One velocity monte carlo for the rod problem with advection-diffusion of DNPs

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

NRE 6103 Project - Collision Probability Method

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

Backwards raytracing simulator for polarized neutron imagers.

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.

Open technical release of the Cognitive Supernova Generator (CSG) fusion‑fission hybrid reactor: OpenMC neutronics model, materials, safety, and Peaceful Use–only license for ocean cleanup, waste transmutation, and humanitarian energy.

Implementation of the Ronen Method in 1D geometries

Python-based Monte Carlo (MC) simulation of neutron transport through a heterogeneous medium.

🌐 Power ocean cleanup and energy production with the CSG, a safe fusion-fission hybrid reactor designed for environmental restoration and waste transmutation.