eng Oriental Scientific Publishing Company Biomedical and Pharmacology Journal 0974-6242 2015-04-28 6 2 137 143 10.13005/bpj/396 2657 article Ali Yadollahpour 1 Mansour Zabihzadeh 1,2 FoadGoli Ahmadabad 3 Department of Medical Physics, School of Medicine, Ahvaz Jundishapur University of Medical Sciences, Ahvaz, Iran. Department of Radiation Oncology, Golestan Hospital, Ahvaz, Jundishapur University of Medical Sciences, Ahvaz, Iran. Department of Medical Physics, School of Medicine, Ahvaz Jundishapur University of Medical Sciences, Ahvaz, Iran. Determining dose distribution around the brachytherapy sources is crucial to establish an accurate treatment planning. In this study dosimetric parameters of 252CF as neutron brachytherapy source were calculated using Monte Carlo simulation method.Physical and geometrical parameters of 252CF source were simulated by MCNPX (2.6.0)modeling code. Air kerma strength, Sk, of source positioned inside a vacuum sphere was calculated. Recommended dosimetric parameters by AAPM, TG-43 protocol were calculated by centering source in a homogeneity phantom.The air kerma strength of 252CF source was estimated 0.345 (cGycm2/¼gh). Dose rate constant was 7.014 cGyh-1U-1. The Radial dose function with 5 degree equation was estimated by gN(r) = 1.1745+0.2298r+0.061r2+-0.0109r3+0.0009r4+-3E10-5r5. Numerical amounts of the anisotropy dose functions and the related equations were calculated.Despite low-energy emission photons and high dose gradients with radial distance, dosimetric parameters of the model 6711 I-125 source can be calculated by MCNPX Monte Carlo code with acceptable accuracy. Calculated parameters of the model 6711 I-125 brachytherapy source can be used by treatment planning systems for brachytherapy. https://biomedpharmajournal.org/vol6no2/calculation-of-dose-distribution-around-a-clinical-252cf-source-for-neutron-therapy-based-on-aapm-tg-43-protocol/ Brachytherapy Neutron dosimetry 252CF Source Monte Carlo Simulation