Conversion coefficients calculation of mono-energetic photons from air-kerma using Monte Carlo and analytical methods

Radiation Safety Assessment in Prostate Cancer Treatment: A Predictive Approach for I-125 Brachytherapy

“…Therefore, the external radiation dose rate is positively correlated with the sum of the source activities of the implanted radioactive nuclei and negatively correlated with the implantation depth of the radioactive source. In the predictive model, we must consider the initial dose rate of I-125 implantation [initial dose rate (D 0 ) in water = S k •Λ] [16][17][18][19][20] and the air-kerma strength and H*(10) conversion factor [21][22][23][24][25][26]. The equations for this are as follows:…”

“…where S k is the total air-kerma strength of all sources implanted; Λ is the dose rate constant, which is the dose rate of the unit air-kerma strength source on the horizontal axis 1 cm away from the water in the water phantom; and CF is the conversion factor that converts air-kerma strength into ambient dose rate equivalent H*(10) (Sv/Gy) [21][22][23][24][25][26]. The average energy of the I-125 source used in this study was 27.4 keV, and the dose rate conversion factor for the external photon air exposure dose rate was calculated from the ICRP-74 (ICRP, 1997) [14].…”

Design and evaluation of structural shielding of a typical radiotherapy facility using egsnrc monte carlo code

“…Based on the previous studies, MC simulation has been considered to be the most accurate tool to describe the underlying physical interactions between radiation and matter. EGSnrc MC Software has been successfully used in various dosimetry principles,[ 12 13 ] HVL evaluation of orthovoltage machine,[ 14 ] simulation of radiotherapy treatment units,[ 15 16 17 18 ] beam quality correction factor,[ 19 ] and so forth. Furthermore, previous studies have shown that MC can be used in the evaluation of X-rays transmission through some shielding materials,[ 11 ] evaluation of the attenuation coefficient of personal radiation shielding protective clothing,[ 20 ] determination of shielding properties of concrete,[ 21 ] shielding analysis,[ 22 ] and the simulation of X-ray room shielding in diagnostic radiology.…”

Neutron conversion coefficients of ambient dose equivalent and personal dose equivalent

“…So, the operational quantities seek to provide a reasonable estimate of the protection quantities. [4][5][6][7][8][9][10] The equivalent dose in the tissue or an organ, H, have given by: 𝐻 = ∑ 𝑤 𝑅 𝐷 𝑇,𝑅 𝑅 Eq .1 Where: DT,R is the main absorbed dose in the specified tissue or organ T from the radiation of type R. wR is the radiation weight factor for neutron given by Equation 2. 11 𝑤 𝑅 = , 𝐸 𝑛 > 50𝑀𝑒𝑉 )…”