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Tally and geometry definition influence on the computing time in radiotherapy treatment planning with MCNP Monte
1Dept. de Ingenieria Quimica y Nucl., Univ. Politecnica de Valencia, Valèncial, Spain.
Abstract:
The present work has simulated the photon and electron transport in a Theratron 780 (MDS Nordion) (60)Co radiotherapy unit, using the Monte Carlo transport code, MCNP (Monte Carlo N-Particle), version 5. In order to become computationally more efficient in view of taking part in the practical field of radiotherapy treatment planning, this work is focused mainly on the analysis of dose results and on the required computing time of different tallies applied in the model to speed up calculations.
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