We present a computing framework for Monte Carlo simulation of radiation transport. In conformity with our belief that Monte Carlo studies should be anchored to physics but not to any particular code, we have enabled different Monte Carlo codes in this environment. The framework embraces the EGSnrc family, FLUKA, MCNP/MCNPX, GEANT4 and PENELOPE; dedicated and non-dedicated resources; shared and...

The most recent release of photonuclear interaction data for Monte Carlo applications is the ENDF/B-VII library. While this current version offers several improvements over its predecessors, it does not address the observed, sometimes quite significant variance in the measured data. For instance, for U, the cross-section data in the ENDF/B-VII library is consistently larger than all measurement...

background: gold nanoparticles are emerging as promising agents for cancer therapy and are being investigated as drug carriers, photothermal agents, contrast agents and radiosensitisers. objective: the aim of this study is to understand characteristics of secondary electrons generated from interaction of gold nanoparticles gnps with x-rays as a function of nanoparticle size and beam energy and ...

Dose to the total body from induced radiation resulting from primary exposure to radiotherapeutic beams is not detailed in routine treatment planning though this information is potentially important for better estimates of health risks including secondary cancers. This information can also allow better management of patient treatment logistics, suggesting better timing, sequencing, and conduct ...

background: hadron therapy for malignant tumor is becoming increasingly popular. there are many factors which effect on implementation of a proper treatment planning. the purpose of this work is to investigate the inhomogeneity effects as affecting factor on proton range, full width at half maximum (fwhm) and 20% position of penumbra (p20) by mcnpx code. materials and methods: an inhomogeneous ...

This study intends to predict the scope of neutron production and induced radioactivity for two therapy accelerators in Taiwan: 235 MeV proton and 400 MeV/A carbon ion accelerators. For radiation safety concern, much effort has been put into associated benchmark calculations to ensure the quality of predictions. Two Monte Carlo codes FLUKA and MCNPX were applied to calculate the neutron yield f...

Monte Carlo simulations are widely used for calculation of the dosimetric parameters of brachytherapy sources. MCNP4C2, MCNP5, MCNPX, EGS4, EGSnrc, PTRAN, and GEANT4 are among the most commonly used codes in this field. Each of these codes utilizes a cross-sectional library for the purpose of simulating different elements and materials with complex chemical compositions. The accuracies of the f...