Enabling particle transport on CAD-based geometries for radiation simulations with penRed

This publication has 13 references indexed in Scilit:

• Comparison between EGSnrc, Geant4, MCNP5 and Penelope for mono-energetic electron beams
  Physics in Medicine & Biology, 2015
• A Comparison between GATE and MCNPX monte carlo codes in simulation of medical linear accelerator
  Journal of Medical Signals & Sensors, 2014
• DagSolid: a new Geant4 solid class for fast simulation in polygon-mesh geometry
  Physics in Medicine & Biology, 2013
• MCNP6 Unstructured Mesh Initial Validation and Performance Results
  Nuclear Technology, 2012
• Acceleration techniques for the direct use of CAD-based geometry in fusion neutronics analysis
  Fusion Engineering and Design, 2010
• Yet Faster Ray-Triangle Intersection (Using SSE4)
  IEEE Transactions on Visualization and Computer Graphics, 2009
• penMesh—Monte Carlo Radiation Transport Simulation in a Triangle Mesh Geometry
  IEEE Transactions on Medical Imaging, 2009
• Geant4—a simulation toolkit
  Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2003
• Development of General-Purpose Particle and Heavy Ion Transport Monte Carlo Code
  Journal of Nuclear Science and Technology, 2002
• A Fast, Matrix-free Implicit Method for Compressible Flows on Unstructured Grids
  Journal of Computational Physics, 1998