neutron-transport

OpenMC Monte Carlo Code

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

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

THOR is a radiation transport code for unstructured meshes.

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

Monte Carlo neutron transport in C99. GPU via Booth (AMD MI300X, NVIDIA RTX). ENDF/B-VII.1 nuclear data. Validated against ICSBEP benchmarks.

An unstructured mesh library for automated method of characteristic mesh generation

Energy-dependent neutron transport Monte Carlo implemented in Rust.

An open-source MOOSE-based radiation transport and fluid activation solver.

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

C library for loading, querying, visualizing, and converting MCNP and OpenMC CSG geometry models

Neutron transport solver using collision probability method

Solves the RTE using the MOC on tetraedral meshes

One Dimensional Neutron Transport Solver

This repository holds various models and benchmarks

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.

A point kernel code for neutron and photon shielding calculations including buildup factor calculation and Gaussian Processes fitting

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.

Monte Carlo neutron transport simulation with neural-network surrogate models for fast transmission prediction.