OpenMC Monte Carlo Code

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

Toolkit for Monte Carlo simulation of ionizing radiation — Trousse d'outils logiciels pour la simulation Monte Carlo du rayonnement ionisant

Stochastic Calculator Of Neutron transport Equation

MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

MC/DC: Monte Carlo Dynamic Code

Parallel Engine for Radiation Energy Deposition

egs_brachy is an application for doing Monte Carlo brachytherapy simulations based on EGSnrc/egs++.

THOR is a radiation transport code for unstructured meshes.

A simple method to solve spherical harmonics moment systems, such as the the time-dependent PN and SPN equations, of radiative transfer in 1D-3D geometry.

TREKIS-3: Time-Resolved Electron Kinetics in SHI-Irradiated Solids

MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.

UMT (Unstructured Mesh Transport) is an LLNL ASC proxy application (mini-app) that solves a thermal radiative transport equation using discrete ordinates (Sn). It utilizes an upstream corner balance method to compute the solution to the Boltzmann transport equation on unstructured spatial grids.

Optimisation for topas Monte Carlo

1-D hydrodynamics code for planetary atmosphere accretion and escape simulations

(M)onte Carlo (I)nteraction and (D)osimetry (S)imulation of (X)-Rays. WIP senior thesis project at Saint Vincent College.

Organization website

Implicit Monte Carlo radiation transport a la Fleck and Cummings 1971