OpenMC Monte Carlo Code
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Updated
May 22, 2024 - Python
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 a Python library (API) to read, edit, and write MCNP input files.
Parallel Engine for Radiation Energy Deposition
egs_brachy is an application for doing Monte Carlo brachytherapy simulations based on EGSnrc/egs++.
MC/DC: Monte Carlo Dynamic Code
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.
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
THOR is a radiation transport code for unstructured meshes.
Optimisation for topas Monte Carlo
MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.
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.
Implicit Monte Carlo radiation transport a la Fleck and Cummings 1971
Fork of the GEOUNED conversion tool for CAD and CSG geometries
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