A fast Monte Carlo code for proton transport in radiation therapy based on MCNPX
نویسندگان
چکیده
منابع مشابه
Assessment of secondary particles in breast proton therapy by Monte Carlo simulation code using MCNPX
Background: The present study aimed to investigate the equivalent dose in vital organs, including heart and lung, due to secondary particles produced during breast proton therapy. Materials and Methods: The numerical ORNL female-phantom was improved and simulated using the Monte Carlo MCNPX code. The depth-dose profile of proton beams with different energies was simulated. The proper energy ran...
متن کاملAn Approach in Radiation Therapy Treatment Planning: A Fast, GPU-Based Monte Carlo Method
Introduction: An accurate and fast radiation dose calculation is essential for successful radiation radiotherapy. The aim of this study was to implement a new graphic processing unit (GPU) based radiation therapy treatment planning for accurate and fast dose calculation in radiotherapy centers. Materials and Methods: A program was written for parallel runnin...
متن کاملModelling Radiation Transport in Voxel Geometries with the Monte Carlo Code Mcnpx
Numerical methods for the simulation of radiation transport, in particular Monte Carlo techniques, are playing a fundamental role in the field of dosimetry for radiation protection. For the last 30 years or so, reference quantities have been since about 30 years calculated relying on mathematical analytical human phantoms representative of the standard man. These calculations, in large part bas...
متن کاملProton Therapy of eye using MCNPX code
Introduction: Proton radiotherapy is the one of advanced teletherapy methods. The protons deposit their maximum energy in a position called Bragg peak. Therefore, for treatment of cancer, the tumor should be placed at the Bragg peak or SOBP. The scattered photons and neutrons is a challenge in proton radiotherapy. The aim of this study is calculation of absorbed dose from scatt...
متن کاملDesign and Simulation of Photoneutron Source by MCNPX Monte Carlo Code for Boron Neutron Capture Therapy
Introduction Electron linear accelerator (LINAC) can be used for neutron production in Boron Neutron Capture Therapy (BNCT). BNCT is an external radiotherapeutic method for the treatment of some cancers. In this study, Varian 2300 C/D LINAC was simulated as an electron accelerator-based photoneutron source to provide a suitable neutron flux for BNCT. Materials and Methods Photoneutron sources w...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
ژورنال
عنوان ژورنال: Journal of Medical Physics
سال: 2014
ISSN: 0971-6203
DOI: 10.4103/0971-6203.139004