Calculation of Dosimetric Parameters for 252Cf-AT Brachytherapy Source using Monte Carlo Simulation

Background and Objective: Nowadays, the use of simulation for accurate determination of dosimetric parameters is inevitable. In this study dosimetric parameters 252CF-AT as a neutron brachytherapy sources using Monte Carlo simulation was calculated for treatment planning of some uterus and brain tumors. Materials and Methods: Thephysical and geometrical characteristic of 252Cf-AT source were estimated by MCNPX (2.6.0) code and the air kerma strength of the source placed inside the vacuum sphere was calculated. Recommended dosimetric parameters by AAPM, TG-43 protocol were determined for source positioned in a homogeneity water phantom. Results: The air kerma strength of 252 Cf source was estimated 0.33 (cGycm2/μg.h). The neutron dose rate constant using *F8 and F6 tallies was calculated 5.7524 (cGy/U.h), 5.650816 (cGy/U.h) respectively. The radial dose function with 5 degree equation was obtained. Numerical amounts of the anisotropy dose functions and the related equations were also calculated. Conclusion: The calculated dosimetric parameters of the model 252Cf-AT source by Monte Carlo code are in good agreement with experimental results and previous calculations. The calculated values can be used by treatment planning systems for the 252Cf-AT source brachytherapy.