MCDB Monte Carlo Code with Fast Track Technique and Mesh Tally Matrix for BNCT

Abstract

The MCDB Monte Carlo Dosimetry Code for Brain Tumors has been developed for Boron Neutron Capture Therapy (BNCT). This code system includes a medical preprocessor, a Monte Carlo dose calculation and a postprocessor. The center point method is used to determine the material and density in each voxel. For dose calculations, a fast particle track technique is developed for the voxel model. This technique is valid for the single-voxel model as well as the multivoxel model. The material matrix and mesh tally matrix are designed for reducing the initialization and tally times. The same dose results as MCNP are achieved. MCDB is faster by a factor of 2:7~3:5 in computational speed with respect to MCNP. Furthermore, MCDB can do parallel computation. It meets the clinical requirements for precision and time.