Penetrability of γ/
            <i>n</i>
            and Static Behavior of Newly Developed Concrete Using Different Passive Assay Techniques

Abdel‐Rahman, Mohamed A.E.; Ali, Mohamed A. E. M.; El‐Mongy, Sayed A.

doi:10.1080/00295450.2019.1697173

Cited by 9 publications

(6 citation statements)

References 13 publications

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“…Despite the apparent considerable divergence at low energies between the exposure rate with and without the buildup factor, the values themselves are minimal. This means that build up factor calculations are not necessary for various applications [29–30] …”

Section: Resultsmentioning

confidence: 99%

“…This means that build up factor calculations are not necessary for various applications. [29][30] The thickness of each other type of samples is calculated to give the same effect as PTA-40 sample. As can be seen from Figure 14, all other samples must have a larger thickness than PTA-40 sample in order to achieve the same shielding efficiency.…”

Section: Radiation Shielding Propertiesmentioning

confidence: 99%

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A comparative Study Between Fluka and Microshield Modeling Calculations to study the Radiation‐Shielding of Nanoparticles and Plastic Waste composites

El-Taher

Zakaly

Pyshkina

et al. 2021

Zeitschrift anorg allge chemie

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A comparative study has been conducted by using Monte Carlo FLUKA code and Microshieldsoftware programs to study the radiation shielding properties of plastic waste mixed with nano copper oxide (CuO) and phosphotungstic acid (PTA). The variousdiverse percentages of new nanocomposite have been prepared using the compression moulding technique, then they are characterized using Fourier transfer infrared spectrophotometer (FT-IR), thermal gravimetric analysis (TGA), X-ray diffraction (XRD). The new nanocomposite has been established as a effective shielding material towards gamma radiation due to the presence of dense materials, like nano copper oxide and phosphotungstic acid. The gamma radiation attenuation has been established by using the previously mentioned methods.The results have proved that the mass attenuation coefficients (μ m ) and effective atomic (Z eff ), and electron densities (N el ) of the samples increased with increasing the phosphotungstic acid (PTA) content while the half-value layer (HVL), the tenth value layer (TVL), and the mean free path (MFP) decreased as PTA increased. Experimental Work Chemicals and MaterialsAll the chemicals in this work have been used without any purification, sodium hydroxide NaOH (FW 40 g mol À 1 and assay > 99 %, BDH company, UK); Copper (II) acetate Cu(CH 3 COO) 2 (FW 181.63 g mol À 1 and assay > 98 %, Sigma-Aldrich Company, USA);

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Section: Resultsmentioning

confidence: 99%

Section: Radiation Shielding Propertiesmentioning

confidence: 99%

A comparative Study Between Fluka and Microshield Modeling Calculations to study the Radiation‐Shielding of Nanoparticles and Plastic Waste composites

El-Taher

Zakaly

Pyshkina

et al. 2021

Zeitschrift anorg allge chemie

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“…Neutron radiography offers an essential validation to radiographic examinations in the field of nondestructive testing (NDT), in addition to the well-known radiographic examinations with x-rays and -rays. [11] Neutrons are absorbed by some light materials, such as hydrogen, boron, and lithium, in contrast to x-rays, yet they pass through many heavier materials [12]. In addition to being a significant instrument for the analysis of radioactive materials, neutrons may even discriminate between various isotopes.…”

Section: Principle Of Ccd -Neutron Cameramentioning

confidence: 99%

Multivariate Image Analysis for Core Monitoring in PWRs

Mohsen,

Nagla,

Elsamahy

et al. 2023

J. Phys.: Conf. Ser.

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In pressurized water reactor (PWR) it is crucial for the operator to monitor the reactor parameters at the same time, such as temperature, pressure, boron concentration, control rod position, coolant density, etc., in order to make proper decision. However, the huge size of data reading from the different instrumentations, in addition to the limited human ability to visually detect, interpret, assess add a lot of uncertainty to the operator qualitative and quantitative analysis of the reactor performance. Therefore, this paper proposes the utilization of radial thermal flux maps (Neutron Images) technique, positioned on the reactor core as a sensitive monitoring technique for all changes of the reactor parameters as a result of the position of the control rods changing. Hence, the features contained in these neutron images are extracted (Multivariate image analysis and regression) via Principal Component Analysis (PCA), and Cluster Analysis (Dendrogram). To determine the effectiveness of the suggested technique in determining the location of the control-rods, several simulations are run. The 3D TRITON FORTRAN-code was utilized to simulate the radial thermal neutron flux of the Westinghouse 2775-MWth PWR benchmark at 100% thermal power generation. The SIMCA software programme is used to develop, test, and generalise the PCA model. Additionally, clustering analysis (CA) is carried out using the statistics software programme Minitab in order to demonstrate the effectiveness of the suggested method.

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“…[1] The Thermoluminescence dosimetry (TLDs) is a widely used dosimetric technique in medical physics staff radiation detection, radiological monitoring of the environment [2] and as a measurement mean for attenuation of ionizing radiation occurred by radioactive shelters as in the measurement of concrete capability to attenuate γ-rays during passing through it. [3][4][5] Thermoluminescence (TL) phenomenon is the emission of light during the thermal stimulation of the investigated insulator or semiconductor following a previous absorption of energy from an ionizing radiation in the form of trapped charges. [6] The photocurrent created induced by the PMT affected by annealing process before the readout process.…”

Section: Introductionmentioning

confidence: 99%

“…Radiation dosimetry has played a crucial role within the field of personnel radiation protection from exposure to hazardous ionizing radiation as electromagnetic radiation (γ‐rays and X‐rays), beta particles (β), and neutrons [1] . The Thermoluminescence dosimetry (TLDs) is a widely used dosimetric technique in medical physics staff radiation detection, radiological monitoring of the environment [2] and as a measurement mean for attenuation of ionizing radiation occurred by radioactive shelters as in the measurement of concrete capability to attenuate γ‐rays during passing through it [3–5] . Thermoluminescence (TL) phenomenon is the emission of light during the thermal stimulation of the investigated insulator or semiconductor following a previous absorption of energy from an ionizing radiation in the form of trapped charges [6] .…”

Section: Introductionmentioning

confidence: 99%

A Co‐Precipitated α‐Alumina (Al₂O₃) used as a TL‐Micro Dosimeter

Said

Tantawy

El-Faramawy

et al. 2021

Zeitschrift anorg allge chemie

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This study describes the preparation method of alumina (Al 2 O 3 ) as a type of thermoluminescence dosimeter (TLD) to monitor gamma photons (γ-rays) in abroad band of radioactive doses (0.5 : 2000 Gy). Alumina is selected in this study because it has a relatively low cost TL material and can be easily prepared. Aluminum oxide (Al 2 O 3 ) was chemically prepared using two different methods which are the Sol-Gel and Co-precipitation methods. For each method, the produced alumina (Al 2 O 3 ) was divided into 4 groups which was thermally treated at (400, 600, 800, 1100°C) respectively for 6 hours for each group. The crystalline features, morphology and sample composition of the prepared samples were chemically characterized by X-ray diffraction (XRD), Scanning Electron Microscopy (SEM) and Energy Dispersive X-ray (EDX). Al 2 O 3 prepared by the Coprecipitation method which was treated at 1100°C (P4) was found to exhibit the highest gamma ray response compared to other samples. The deconvolution analysis showed that the main TL glow curve consisted of ( 5) overlapped peaks corresponding to number of traps. The linearity of the gamma response for this sample appeared in doses ranging from 1 Gy up to 200 Gy. The minimum detectable dose that can be detected by precipitated-alumina sample (P1) was calculated mathematically to be 3.653 mGy. The fading was found to be 45.6 % after being stored for 45 days at room temperature and approximately 65 % after 90 days. This sample was reproducible according to the repeated TL results for the same sample for 5 times as their values were very close from one other with standard deviation (� σ) 0.96 %. Henceforth, Co-precipitated αalumina can be used as a TL-Micro dosimeter.

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Penetrability of γ/ n and Static Behavior of Newly Developed Concrete Using Different Passive Assay Techniques

Cited by 9 publications

References 13 publications

A comparative Study Between Fluka and Microshield Modeling Calculations to study the Radiation‐Shielding of Nanoparticles and Plastic Waste composites

A comparative Study Between Fluka and Microshield Modeling Calculations to study the Radiation‐Shielding of Nanoparticles and Plastic Waste composites

Multivariate Image Analysis for Core Monitoring in PWRs

A Co‐Precipitated α‐Alumina (Al₂O₃) used as a TL‐Micro Dosimeter

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Penetrability of γ/ n and Static Behavior of Newly Developed Concrete Using Different Passive Assay Techniques

Cited by 9 publications

References 13 publications

A comparative Study Between Fluka and Microshield Modeling Calculations to study the Radiation‐Shielding of Nanoparticles and Plastic Waste composites

A comparative Study Between Fluka and Microshield Modeling Calculations to study the Radiation‐Shielding of Nanoparticles and Plastic Waste composites

Multivariate Image Analysis for Core Monitoring in PWRs

A Co‐Precipitated α‐Alumina (Al2O3) used as a TL‐Micro Dosimeter

Contact Info

Product

Resources

About

A Co‐Precipitated α‐Alumina (Al₂O₃) used as a TL‐Micro Dosimeter