• Title/Summary/Keyword: Gamma spectrometer

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Assessment of radioactivity levels and radiation hazards in building materials in Egypt

  • Ahmed E. Abdel Gawad;Mohamed Y. Hanfi;Mostafa N. Tawfik;Mohammed S. Alqahtani;Hamed I. Mira
    • Nuclear Engineering and Technology
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    • v.56 no.2
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    • pp.707-714
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    • 2024
  • Different degrees of natural radioactivity found in quartz can have negative consequences on health. Quartz vein along the investigated Abu Ramad area, Egypt, had its natural radioactivity assessed. The HPGe spectrometer was used to determine the role played by the radionuclides 238U, 232Th, and 40K in the gamma radiation that was emitted, and the results showed that these concentrations are 484.64 ± 288.4, 36.8 ± 13.1 and 772.2 ± 134.6 Bq kg-1 were higher than the corresponding reported global limits of 33, 45, and 412 Bq kg-1 for each radionuclide (238U, 232Th, and 40K). Among the radiological hazard parameters, the excess lifetime cancer risk (ELCR) is estimated and it's mean value of ELCR (1.2) is higher than the permissible limit of 0.00029. The relationship between the radionuclides and the associated radiological hazard characteristics was investigated based on multivariate statistical methods including Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA). According to statistical research, the radioactive risk of quartz is primarily caused by the 238U, 232Thand 40K. Finally, applying quartz to building materials would pose a significant risk to the public.

Radiological hazards assessment associated with granitoid rocks in Egypt

  • Ahmed E. Abdel Gawad;Masoud S. Masoud;Mayeen Uddin Khandaker;Mohamed Y. Hanfi
    • Nuclear Engineering and Technology
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    • v.56 no.6
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    • pp.2239-2246
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    • 2024
  • The present study aimed to assess the radioactive hazards associated with the application of granitoid rocks in building materials. An HPGe spectrometer was used to detect the levels of the radioactive elements uranium-238, thorium-232, and potassium-40 in the granitoid rocks. The results showed that the levels of these elements were lower (38.32 < 33 Bq kg-1), comparable (47.19-45 Bq kg-1) and higher (992.26 ≫> 412 Bq kg-1) than the worldwide limits for 238U, 232Th, and 40K concentration, respectively. The exposure to gamma radiation of granitoid rocks was studied by various radiological hazard variables like the absorbed dose rate (Dair), the outdoor and indoor annual effective dose (AEDout and AEDin), and excess lifetime cancer risk (ELCR). A variety of statistical methods, including Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA) was used, to study the relationship between the radioactive elements and the radiological hazards. According to statistical analysis, the main radioactive risk of granitoid rocks is contributed to by the elements uranium-238, thorium-232, and potassium-40. Granitoid rocks can be applied in building materials, but under control to prevent risk to the public.

The radioactivity levels and beta dose rate assessment from dental ceramic materials in Egypt

  • Mohamed Hasabelnaby;Mohamed Y. Hanfi;Hany El-Gamal;Ahmed H. El Gindy;Mayeen Uddin Khandakerf;Ghada Salaheldin
    • Nuclear Engineering and Technology
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    • v.56 no.9
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    • pp.3898-3903
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    • 2024
  • There is a lack of available data on the radioactivity levels of these materials, despite the potential risks they may pose to patients, dental technicians, and dentists. A total of forty samples were collected from different dental markets in Egypt. Using an NaI(Tl) detector, the gamma-ray spectrometer measured the activity levels of uranium-238, radium-226, thorium-232, and potassium-40. The findings revealed that the mean concentration of 238U (below the minimum detectable activity, MDA), 226Ra (135 ± 5 and 132 ± 5 Bq/kg), 232Th (187 ± 4 and 243 ± 8 Bq/kg), and 40K (1560 ± 52 and 2501 ± 89 Bq/kg) in feldspar and zirconia (ZrO2) dental ceramic samples, respectively, were all within the limits established by the International Organization for Standardization (ISO) and the European Commission (EC). The use of feldspar and zirconia dental ceramics to restore all teeth would result in an estimated maximum beta dose of 1.5 mGy/year to the oral tissue. The results suggest that there is no cause for concern regarding any additional beta dose to the oral cavity from the use of feldspar and zirconia dental ceramics.

Effect of Gamma-Irradiation on the Volatile Flavor Compounds from Dried Ginger (Zingiber officinale Roscoe) (건조생강의 감마선 조사에 의한 휘발성 향기성분 변화)

  • No, Ki-Mi;Seo, Hye-Young;Gyawali Rajendra;Shim, Seong-Lye;Yang, Su-Hyeong;Lee, Sung-Jin;Kim, Kyong-Su
    • Journal of the Korean Society of Food Science and Nutrition
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    • v.34 no.6
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    • pp.892-898
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    • 2005
  • The effect of gamma irradiation on volatile components of Korean dried ginger (Zingiber officinale Roscoe) was studied and compared with non-irradiated sample. Volatile compounds from non- and irradiated samples were extracted using simultaneous distillation-extraction (SDE) apparatus and analyzed by gas chromatography-mass spectrometer (GC/MS). A total of 83 and 71 compounds were identified and quantified from non-and irradiated dried ginger at dose of 10 kGy. Identified components were hydrocarbons, alcohols, aldehydes, esters, ketones and miscellaneous compounds. The terpenoid compounds in volatile flavor compounds identified from non and irradiatied dried ginger were $98.27\%\;and\;98.12\%$, respectively. $\alpha$ -zingiberene,$\beta$-sesquiphelland reno, geranial, (Z,E) $\alpha$ -farnesene, $\beta$ -phellandene were detected as major volatile compounds of two experimental sample. The amount of volatile components in the samples was changed by irradiation but the profile of volatiles in non- and irradiated dried ginger were the same.

Radioactive Concentrations in Chemical Fertilizers

  • Gwang-Ho Kim;Jae-Hwan Cho
    • Journal of Radiation Protection and Research
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    • v.47 no.4
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    • pp.195-203
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    • 2022
  • Background: The aim of the present study was to determine radioactive concentrations in fertilizers known to contain essential nutrients. Results of this study could be used as basic data to monitor the impact of chemical fertilizers on the environment and public health. Nitrogen fertilizers, calcium fertilizers, sulfur fertilizers, phosphate acid fertilizers, and potassium chloride fertilizers were used in this study. Materials and Methods: Five chemical fertilizers were pulverized, placed in polyethylene containers, and weighed. The time to measure each specimen was set to be 3,600 seconds for a scintillator-based gamma-ray spectroscopy system. Concentration of gamma radionuclide was analyzed based on obtained spectra. At the end of the measurement, the spectrum file was stored and used to calculate radioactive concentrations using a gamma-ray spectrometer software. Results and Discussion: In the nitrogen fertilizer, 3.49 ± 5.71 Bq/kg of 137Cs, 34.43 ± 7.61 Bq/kg of 134Cs, and 569.16 ± 91.15 of 40K were detected whereas 131I was not detected. In the calcium fertilizer, 5.74 ± 4.40 Bq/kg of 137Cs (the highest concentration among all fertilizers), 22.37 ± 5.39 Bq/kg of 134Cs, and 433.67 ± 64.24 Bq/kg of 40K were detected whereas 131I was not detected. In the sulfur fertilizer, 347.31 ± 55.73 Bq/kg of 40K, 19.42 ± 4.53 Bq/kg of 134Cs, 2.21 ± 3.49 of 137Cs, and 0.04 ± 0.22 Bq/Kg of 131I were detected. In the phosphoric acid fertilizer, 70,007.34 ± 844.18 Bq/kg of 40K (the highest concentration among all fertilizers) and 46.07 ± 70.40 Bq/kg of 134Cs were detected whereas neither 137Cs nor 131I was detected. In the potassium chloride fertilizer, 12,827.92 ± 1542.19 Bq/kg of 40K was and 94.76 ± 128.79 Bq/kg of 134Cs were detected whereas neither 137Cs nor 131I was detected. The present study examined inorganic fertilizers produced by a single manufacturer. There might be different results according to the country and area from which fertilizers are imported. Further studies about inorganic fertilizers in more detail are needed to create measures to reduce 40K. Conclusion: Measures are needed to reduce radiation exposure to 40K contained in fertilizers including phosphoric acid and potassium chloride fertilizers.

Study of 4π Compton Suppression Spectrometer by Monte Carlo Simulation (몬테카를로 시뮬레이션을 통한 4π 컴프턴 억제 분광기 연구)

  • Jang, Eun-Sung;Lee, Hyo-Yeong
    • Journal of the Korean Society of Radiology
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    • v.11 no.3
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    • pp.123-129
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    • 2017
  • Compton suppression apparatus using the Compton scattering response, by inhibiting part of the spectrum Compton continuum Compton continuum in the area of the peak analysis of the gamma rays that enables a clearer device. In order to find out the geometry structure of high-purity germanium detector(HPGe) -NaI(TI) and to optimize the effect of movement, Monte Carlo simulation was used to grasp the behavioral characteristics of Compton suppression and compare several layout structures. And applied to the cylinder beaker used for the environmental measurement by using the efficiency according to the distance. For the low-energy source such as 81 keV, the Compton continuum is scarcely developed and the suppression effect is also insignificant because the scattering cross-section of the Compton effect is relatively low. In the spectrum for the remaining energy, it can be seen that the Compton continuum part is suppressed in a certain energy range. Compton suppression effect was not significantly different from positional shift. average reduction factor(ARF) value was about 1.08 for 81 keV and about 1.23 for 1332.4keV energy at the highest value. It can be seen that suppression over the Compton continuum region of the energy spectrum is a more appropriate arrangement. Therefore, it can be applied to various environmental sample measurement through optimized structure.

Validation of a New Design of Tellurium Dioxide-Irradiated Target

  • Fllaoui, Aziz;Ghamad, Younes;Zoubir, Brahim;Ayaz, Zinel Abidine;Morabiti, Aissam El;Amayoud, Hafid;Chakir, El Mahjoub
    • Nuclear Engineering and Technology
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    • v.48 no.5
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    • pp.1273-1279
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    • 2016
  • Production of iodine-131 by neutron activation of tellurium in tellurium dioxide ($TeO_2$) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing of the target by using tungsten inert gaswelding. The leakage rate of all prepared targets was assessed using a helium mass spectrometer. The accepted leakage rate is ${\leq}10^{-4}mbr.L/s$, according to the approved safety report related to iodine-131 production in the TRIGA Mark II research reactor (TRIGA: Training, Research, Isotopes, General Atomics). To confirm the resistance of the new design to the irradiation conditions in the TRIGA Mark II research reactor's central thimble, a study of heat effect on the sealed targets for 7 hours in an oven was conducted and the leakage rates were evaluated. The results show that the tightness of the targets is ensured up to $600^{\circ}C$ with the appearance of deformations on lids beyond $450^{\circ}C$. The study of heat transfer through the target was conducted by adopting a one-dimensional approximation, under consideration of the three transfer modes-convection, conduction, and radiation. The quantities of heat generated by gamma and neutron heating were calculated by a validated computational model for the neutronic simulation of the TRIGA Mark II research reactor using the Monte Carlo N-Particle transport code. Using the heat transfer equations according to the three modes of heat transfer, the thermal study of I-131 production by irradiation of the target in the central thimble showed that the temperatures of materials do not exceed the corresponding melting points. To validate this new design, several targets have been irradiated in the central thimble according to a preplanned irradiation program, going from4 hours of irradiation at a power level of 0.5MWup to 35 hours (7 h/d for 5 days a week) at 1.5MW. The results showthat the irradiated targets are tight because no iodine-131 was released in the atmosphere of the reactor building and in the reactor cooling water of the primary circuit.

Characterization of PET films coated with organic-inorganic hybrid coating system containing surface modified zirconia (표면 개질된 지르코니아를 함유한 유-무기 하이브리드 코팅액으로 도포된 PET 필름의 특성)

  • Lee, Soo;Kim, Sang Yup;Kim, Young Jun
    • Journal of the Korean Applied Science and Technology
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    • v.35 no.3
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    • pp.595-605
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    • 2018
  • In recent years, researches on organic-inorganic coating films have conducted a nanocomposite system composed of organic resin matrices having excellent flexibility and chemical stability and inorganic materials having excellent mechanical properties. The o-phenylphenoxyethyl acrylate (OPPEA) used as the acrylate monomer has a high refractive index of 1.58, and the bisphenol A ethoxylate diacrylate (BAEDA) has a low refractive index but improves the chemical stability of the organic resin. In addition, zirconia used as an inorganic material exhibits excellent durability and optical properties. In this study, the BAEDA contents in acrylate monomer were controlled to produce a film with suitable optical transparency. And optimum conditions were established by comparing the changes in surface properties of PET films detected with pencil hardness tester, Abbe's refractometer, and UV-vis spectrophotometer. The hydrophobicity and the dispersibility of zirconia in acrylate monomer were much improved after modification with ${\gamma}$-methacryloxypropyltrimethoxysilane (MPS), which is a silane coupling agent. And the existence of ester C=O bond peak at $1716cm^{-1}$ introduced by MPS through FT-IR ATR spectrophotometer confirmed the completion of surface modification of zirconia with MPS. In addition, the presence of silicon atom on the surface modified zirconia was also proved using X-ray fluorescence spectrometer. When the photocurable hybrid coating was prepared by introducing chemically modified zirconia into acrylate monomer, the refractive index of this coated PET film was improved by 1.2%, compared to the only acrylate coated PET film. The homogeneous distribution of zirconia in acrylate coating layer on PET film was also identified through SEM/EDS mapping analysis technique.

Detection of Irradiated Milk Formulas using Electron Spin Resonance (전자스핀공명법(ESR)을 이용한 방사선조사 조제유류의 판별)

  • Woon, Jae-Ho;Park, Byeong-Ryong;Choi, Byung-Kook;Kim, Na-Young;Jeong, Hong-Jeom;Cheong, Ki-Soo;Kim, Hee-Sun;Kim, Chang-Seob
    • Journal of Dairy Science and Biotechnology
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    • v.28 no.2
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    • pp.13-18
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    • 2010
  • Electron Spin Resonance (ESR) spectroscopy has been used to detect the presence of radiation-induced free radicals in biological samples since the mid 1950s and to irradiate foods containing cellulose, crystalline sugar, and bone. Therefore, we analyzed the ESR spectrum of irradiated infant formula and its ingredients in this study. Samples were irradiated with 2 different radiation sources of $^{60}Co$ gamma rays and electron beams (EBs), and the absorbed doses were 0, 1, 3, 5, and 7 kGy. ESR measurements were performed under normal atmospheric conditions using a JEOL JES-FA100 spectrometer equipped with an X-band bridge. Irradiated infant formula showed anunsymmetrical spectrum ($g_1$=2.0050, $g_2$=2.0006); in contrast, non-irradiated samples showed asymmetrical spectrum. The ingredients of irradiated samples showed a multi-component ESR signal in glucose and lactose and a singlet-type spectrum in milk powder (g=2.0050). $R^2$ of the dose-response curve showed a fine linearity of over 0.95 across the entire sample. We also compared the spectra of identical samples irradiated with $^{60}Co$ gamma rays and EBs, because EBs can be used for food irradiation in foreign countries, although this is not permitted in Korea. However, we could not find any significant differences according to the types of radiation source. Thus, ESR spectroscopy can be used to detect irradiated infant formula and several types of primary ingredients in this formula.

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Antioxidative Activity of Volatile Compounds in Flower of Chrysanthemum indicum, C. morifolium, and C. zawadskii (감국, 국화 및 구절초 꽃 휘발성 성분의 항산화활성)

  • Woo, Koan-Sik;Yu, Jung-Sik;Hwang, In-Guk;Lee, Youn-Ri;Lee, Chul-Hee;Yoon, Hyang-Sik;Lee, Jun-Soo;Jeong, Heon-Sang
    • Journal of the Korean Society of Food Science and Nutrition
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    • v.37 no.6
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    • pp.805-809
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    • 2008
  • The objective of this study was to compare the aroma characteristics and antioxidant activity of Chrysanthemum indicum Linne (CIL), C. morifolium Ramat (CMR) and C. zawadskii var Latilobum (CZL). The volatile compounds were extracted by simultaneous steam distillation extraction and identified with gas chromatography/mass spectrometer. The major volatile compounds of Chrysanthemum sp. were camphene, 1,8-cineole, benzene, pinocarvone, bicyclo-2,2,1-heptan-2-ol, ${\beta}$-caryophyllene, 3-cyclohexen-1-ol, ${\gamma}$-curcumene, zingiberene and ${\beta}$-bisabolene. The DPPH radical scavenging activity (EDA, %) of volatile compounds in CIL, CMR and CZL were 30.57, 46.36, and 51.72%/g sample, respectively. The ascorbic acid equivalent antioxidant capacity (AEAC) of volatile compounds were 34.99, 35.31, and 38.48 mg AEAC/g, respectively.