A detailed investigation of gamma-ray energy absorption and dose buildup factor for soft tissue and tissue equivalents using Monte Carlo simulation

2020 ◽  
Vol 177 ◽  
pp. 109118 ◽  
Author(s):  
Mustafa Mohammad Rafiei ◽  
Hossein Tavakoli-Anbaran ◽  
Murat Kurudirek
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Soft Tissue ◽  
Energy Absorption ◽  
Gamma Ray ◽  
Buildup Factor ◽  
Tissue Equivalents

scholarly journals Monte carlo simulation of different positron emitting radionuclides incorporated in a soft tissue volume

2017 ◽  
Vol 8 (1) ◽  
Author(s):  
Segundo Agustín Martínez Ovalle
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Soft Tissue ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Tissue Volume ◽  
Monte Carlo Calculations ◽  
Soft Tissue Volume ◽  
Maximum Range ◽  
Positron Emitters

Monte Carlo calculations were carried out where compounds with positron-emitters radionuclides, like FDG (18F), Acetate (11C), and Ammonium (13N), were incorporated into a soft tissue volume, in the aim to estimate the type of particles produced their energies, their mean free paths, and the absorbed dose at different distances with respect to the center of the volume. The volume was modeled with a radius larger than the maximum range of positrons in order to produce 0.511 keV annihilation gamma-ray photons. With the obtained results the absorbed dose, in various organs and tissues able to metabolize different radiopharmaceutical drugs, can be estimated. The code used was GEANT4.

Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding

2020 ◽  
Vol 0 (0) ◽  
Author(s):  
Bünyamin Aygün ◽  
Erdem Şakar ◽  
Abdulhalik Karabulut ◽  
Bünyamin Alım ◽  
Mohammed I. Sayyed ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Fast Neutron ◽  
Cross Sections ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Neutron Shielding ◽  
Shielding Properties ◽  
Effective Neutron ◽  
Simulation Codes

AbstractIn this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.

Gamma-ray energy absorption and exposure buildup factor studies in some human tissues with endometriosis

2011 ◽  
Vol 69 (2) ◽  
pp. 381-388 ◽  
Author(s):  
Murat Kurudirek ◽  
Bekir Doğan ◽  
Metin İngeç ◽  
Neslihan Ekinci ◽  
Yüksel Özdemir
Keyword(s):  
Energy Absorption ◽  
Gamma Ray ◽  
Buildup Factor ◽  
Human Tissues

Precise Monte Carlo simulation of gamma-ray response functions for an NaI(Tl) detector

2002 ◽  
Vol 57 (4) ◽  
pp. 517-524 ◽  
Author(s):  
Hu-Xia Shi ◽  
Bo-Xian Chen ◽  
Ti-Zhu Li ◽  
Di Yun
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Gamma Ray ◽  
Response Functions

Estimation of gamma- and X-ray photons buildup factor in soft tissue with Monte Carlo method

2009 ◽  
Vol 67 (7-8) ◽  
pp. 1438-1440 ◽  
Author(s):  
Dariush Sardari ◽  
Ali Abbaspour ◽  
Samaneh Baradaran ◽  
Farshid Babapour
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Soft Tissue ◽  
Buildup Factor ◽  
X Ray
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