OpenMC Monte Carlo Code
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Updated
Jun 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
MontePy is a Python library (API) to read, edit, and write MCNP input files.
Toolkit for Monte Carlo simulation of ionizing radiation — Trousse d'outils logiciels pour la simulation Monte Carlo du rayonnement ionisant
MC/DC: Monte Carlo Dynamic Code
egs_brachy is an application for doing Monte Carlo brachytherapy simulations based on EGSnrc/egs++.
TREKIS-3: Time-Resolved Electron Kinetics in SHI-Irradiated Solids
Parallel Engine for Radiation Energy Deposition
Stochastic Calculator Of Neutron transport Equation
Fork of the GEOUNED conversion tool for CAD and CSG geometries
(M)onte Carlo (I)nteraction and (D)osimetry (S)imulation of (X)-Rays. WIP senior thesis project at Saint Vincent College.
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
Implicit Monte Carlo radiation transport a la Fleck and Cummings 1971
MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.
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.
1-D hydrodynamics code for planetary atmosphere accretion and escape simulations
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