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.
A Python-based Monte Carlo radiation transport code
Some Monte Carlo tools
Parallel Engine for Radiation Energy Deposition
egs_brachy is an application for doing Monte Carlo brachytherapy simulations based on EGSnrc/egs++.
MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks as a placeholder for the full LSP is implemented.
THOR is a radiation transport code for unstructured meshes.
TREKIS-3: Time-Resolved Electron Kinetics in SHI-Irradiated Solids
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.
Optimisation for topas Monte Carlo
1-D hydrodynamics code for planetary atmosphere accretion and escape simulations
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.
An open-source MOOSE-based radiation transport and fluid activation solver.
C library for loading, querying, visualizing, and converting MCNP and OpenMC CSG geometry models
Photon shielding analysis and engineering design tool with NIST XCOM data, optimization, and OpenMC Monte Carlo benchmarking.
(M)onte Carlo (I)nteraction and (D)osimetry (S)imulation of (X)-Rays. WIP senior thesis project at Saint Vincent College.
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