Abstract:The 4π NaI(Tl) γ-ray detectors are consisted of the well cavity with cylindrical cross section, and the enclosing geometry of measurements with large detection angle. This leads to exceptionally high efficiency level and a significant coincidence summing effect, much more than a single cylindrical or coaxial detector especially in very low activity measurements. In the present work, the detection effective solid angle in addition to both full-energy peak and total efficiencies of well-type detectors, were main… Show more
“…According to linear and nonlinear estimation of PFOK and PFOK models, the experimental qe value is practically similar to that obtained theoretically in the case of PFOK model. The larger rate constant ( K 1 ) of the PFOK model as compared to the smaller rate constant ( K 2 ) of the PSOK model indicates the adsorption process is fast 28 , 29 .…”
Section: Kinetics Aspects; Pseudo-first and Second-order Kinetic Modelsmentioning
Radioactive iodine isotopes especially 131I are used for diagnosis and treatment of different types of cancer diseases. Due to the leak of radioactive iodine into the patient’s urine in turn, the wastewater would be contaminated, so it is worth preparing a novel adsorption green material to remove the radioactive iodine from wastewater efficiently. The removal of 127I and 131I contaminants from aqueous solution is a problem of interest. Therefore, this work presents a new study for removing the stable iodine 127I− and radioactive iodine 131I from aqueous solutions by using the novel nano adsorbent (Nano ZnO/MWCNTs) which is synthesized by the arc discharge method. It is an economic method for treating contaminated water from undesired dissolved iodine isotopes. The optimal conditions for maximum removal are (5 mg/100 ml) as optimum dose with shacking (200 rpm) for contact time of (60 min), at (25 °C) in an acidic medium of (pH = 5). After the adsorption process, the solution is filtrated and the residual iodide (127I−) is measured at a maximum UV wavelength absorbance of 225 nm. The maximum adsorption capacity is (15.25 mg/g); therefore the prepared nano adsorbent (Nano ZnO/MWCNTs) is suitable for treating polluted water from low iodide concentrations. The adsorption mechanism of 127I− on to the surface of (Nano ZnO/MWCNTs) is multilayer physical adsorption according to Freundlich isotherm model and obeys the Pseudo-first order kinetic model. According to Temkin isotherm model the adsorption is exothermic. The removal efficiency of Nano ZnO/MWCNTs for stable iodine (127I−) from aqueous solutions has reached 97.23%, 89.75%, and 64.78% in case of initial concentrations; 0.1843 ppm, 0.5014 ppm and 1.0331 ppm, respectively. For the prepared radio iodine (131I−) solution of radioactivity (20 µCi), the dose of nano adsorbent was (10 mg/100 ml) and the contact time was (60 min) at (pH = 5) with shacking (200 rpm) at (25 °C). The filtration process was done by using a syringe filter of a pore size (450 nm) after 2 days to equilibrate. The removal efficiency reached (34.16%) after the first cycle of treatment and the percentage of residual radio iodine was (65.86%). The removal efficiency reached (94.76%) after five cycles of treatment and the percentage of residual radio iodine was (5.24%). This last percentage was less than (42.15%) which produces due to the natural decay during 10 days.
“…According to linear and nonlinear estimation of PFOK and PFOK models, the experimental qe value is practically similar to that obtained theoretically in the case of PFOK model. The larger rate constant ( K 1 ) of the PFOK model as compared to the smaller rate constant ( K 2 ) of the PSOK model indicates the adsorption process is fast 28 , 29 .…”
Section: Kinetics Aspects; Pseudo-first and Second-order Kinetic Modelsmentioning
Radioactive iodine isotopes especially 131I are used for diagnosis and treatment of different types of cancer diseases. Due to the leak of radioactive iodine into the patient’s urine in turn, the wastewater would be contaminated, so it is worth preparing a novel adsorption green material to remove the radioactive iodine from wastewater efficiently. The removal of 127I and 131I contaminants from aqueous solution is a problem of interest. Therefore, this work presents a new study for removing the stable iodine 127I− and radioactive iodine 131I from aqueous solutions by using the novel nano adsorbent (Nano ZnO/MWCNTs) which is synthesized by the arc discharge method. It is an economic method for treating contaminated water from undesired dissolved iodine isotopes. The optimal conditions for maximum removal are (5 mg/100 ml) as optimum dose with shacking (200 rpm) for contact time of (60 min), at (25 °C) in an acidic medium of (pH = 5). After the adsorption process, the solution is filtrated and the residual iodide (127I−) is measured at a maximum UV wavelength absorbance of 225 nm. The maximum adsorption capacity is (15.25 mg/g); therefore the prepared nano adsorbent (Nano ZnO/MWCNTs) is suitable for treating polluted water from low iodide concentrations. The adsorption mechanism of 127I− on to the surface of (Nano ZnO/MWCNTs) is multilayer physical adsorption according to Freundlich isotherm model and obeys the Pseudo-first order kinetic model. According to Temkin isotherm model the adsorption is exothermic. The removal efficiency of Nano ZnO/MWCNTs for stable iodine (127I−) from aqueous solutions has reached 97.23%, 89.75%, and 64.78% in case of initial concentrations; 0.1843 ppm, 0.5014 ppm and 1.0331 ppm, respectively. For the prepared radio iodine (131I−) solution of radioactivity (20 µCi), the dose of nano adsorbent was (10 mg/100 ml) and the contact time was (60 min) at (pH = 5) with shacking (200 rpm) at (25 °C). The filtration process was done by using a syringe filter of a pore size (450 nm) after 2 days to equilibrate. The removal efficiency reached (34.16%) after the first cycle of treatment and the percentage of residual radio iodine was (65.86%). The removal efficiency reached (94.76%) after five cycles of treatment and the percentage of residual radio iodine was (5.24%). This last percentage was less than (42.15%) which produces due to the natural decay during 10 days.
“…To calculate the 3 ×3 𝛾-ray NaI(Tl) detector efficiency and establish the true full-energy peak efficiency curve for using any radioactive source in a certain shape and at a close location from the detector surface, there are a lot of methods used [11][12][13]. The numerical simulation method (NSM) is considered one of those methods after the routine experimental calibration procedure, which is regarded as an extremely expensive and limited method [15][16][17][18].…”
Section: Jinst 16 P07011mentioning
confidence: 99%
“…The calculations of the coincidence summing corrections (COI) values are slightly more problematical. The approximate system of equations used in methodology [11][12][13] to obtain the estimations values based on the decay scheme style through this work for special energies, to find the true full-energy peak efficiency for the 3 × 3 𝛾-ray NaI(Tl) detector in case of the absence the hexagonal radioactive sources. It's necessary in this situation to determine the effective solid angle, Ω eff (Hexagonal) , total efficiency, 𝜀 T(Hexagonal) , full-energy peak efficiency, 𝜀 P(Hexagonal) , and peak-to-total ratio (P/T) in case of the hexagonal 152 Eu radioactive sources.…”
Section: Mathematical Viewpointmentioning
confidence: 99%
“…Therefore, scientists and technicians tend to make corrections due to these special effects, which are not easy to be done, particularly in the shape of radioactive volumetric sources. In such a situation, complex algorithms and equations build on a large number of details have been expanded to consider the effect of such a phenomenon [10][11][12][13]. The main parameter in the 𝛾-ray spectrometry field that can be used in the coincidence summing corrections is the measured peak-to-total ratio (P/T) for a different set of the…”
Nowadays, many scientists work on the geometry change between source-to-detector arrangement to calibrate the 3”× 3” γ-ray NaI(Tl) detector based on the available sample shape in the laboratory. The calculated full-energy peak efficiency is more sensitive in radiation activity determination and can be estimated build on complex analytical and numerical techniques. In the present study, the full-energy peak and total efficiencies beside the peak-to-total ratio (P/T) for γ-ray NaI(Tl) detector concerning vertical hexagonal ^152Eu radioactive source is calculated for all γ-rays involved in the cascade and estimate the suitable correction for coincidence summing effects (COI) by mean of the numerical simulation method (NSM). The extra factors which cause the γ-ray attenuation taken into consideration as well, such as, source composition materials, “self-attenuation within the source itself”, the detector end cap with the other supporting materials around the detector crystal, the source container material, and the holder used during the measurement process. The theory of this methodology depends on the efficiency transfer technique; calculate the effective solid angle, that be positioned in between the source-to-detector system, besides estimating the path lengths of the γ-rays inside the hexagonal ^152Eu radioactive sources and the active medium inside the detector itself as well. The results gained in the present work gave an agreement between simulation and measured data. The results show that to improve the accuracy of the γ-rays detector efficiency, many technical and methodological aspects of the present method are fitting and possible for applications inside the radiation laboratory, industrial, and medical sectors.
“…The CSC for measuring point and volumetric sources was discussed by several authors regarding calculating the total efficiency or the peak-total ratio using different methods, such as calculating based on Monte Carlo simulation (Arnold and Sima 2001), equations expressed in a matrix form (Semkow et al 1990;Korun and Martin 1993), the code GESPECOR (Sima et al 2001;Arnold and Sima 2004), the code KORSUM and its modification (Debertin and Sch€otzig 1997;Yoon et al 2020), the efficiency transfer code EFFTRAN (Vidmar et al 2011), or the ETNA (Lepy et al 2012), using the effective solid angle calculation to use the numerical procedure (NSM) or ANGLE4 software (Abbas et al 2001(Abbas et al , 2021Badawi et al 2017). The calculating of total efficiency is more difficult, especially for extended sources, and less accurate for voluminous sources, so the present method calculates the CSC factor for point and volumetric sources without calculating the total efficiency using two tracks in Geant4 Monte Carlo simulation.…”
Geant4 simulation is used to calculate peak efficiency and correct the effect of coincidence summing in detecting volumetric gamma-ray sources; this simulation was applied to a standard 152Eu source with different volumes as a test case. The source is a liquid cylindrical shape of various volumes. Peak efficiency was calculated using two tracks in the Geant4 simulation: single-energy track and “monoenergetic Track” without coincidence summing. Here, the energy of the source is known, and the track of radionuclides, including the coincidence summing, depends on the decay scheme of the radioactive source. The ratio between the peak efficiency of the two tracks gives us the correction factor (CF). The experimental method was used to calculate the peak efficiency and was amended by the correction factor computed with Geant4 tracks. The results showed a good agreement between experimental efficiency after correction and free-summing simulated efficiency. The comparison indicated that the present method is valid and useful for voluminous gamma-ray sources.
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