Effect of Different Voxel-uniting Methods on the Dose Calculation of MCNP/MCNPX
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Graphical Abstract
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Abstract
The key problem for the application of the Monte Carlo particle transport code MCNP/MCNPX in radiotherapy is the creation of complex geometrical model. To handle this problem, a software has been developed to automatically create MCNP/MCNPX geometrical model based on the CT images, and three geometric cell treatment schemes were proposed and implemented in this software. In this work, three MCNP models are created, and calculations are performed to investigate the effect of those cell treatment schemes and repeated structure technique on the calculation results.
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