شماره 3 تاریخ انتشار 2019-09

• Estimation of dosimetric parameters of I-125 brachytherapy source model 6711 using GATE8.1 code
• Recovery of thermoluminescence sensitivity in CaF2:Mn (TLD-400) dosimeter under heating process
• Calculation and evaluation of the vital head organs dose during Neutron Therapy in Tehran Research Reactor using Zubal phantom
• Efficiency determination of HPGe detector by simulation and experimental methods for solid volume source
• Study of the absorbed dose rate of all rays emitted from the 252Cf brachytherapy source by the Monte Carlo method
• Comparing X-ray dose reduction capability of silicon-bismuth micro- and nanocomposite shields using chest CT test
• Designing CT scanning rooms and estimating patient and personnel absorbed dose using code (MCNPX 2.6)