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1

Fletcher, John Justice. "Shielding for Beta-gamma Radiation." Health Physics 64, no. 6 (1993): 680–81. http://dx.doi.org/10.1097/00004032-199306000-00017.

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2

Özdemir, Hakan, and Berkay Camgöz. "Gamma radiation shielding effectiveness of cellular woven fabrics." Journal of Industrial Textiles 47, no. 5 (2016): 712–26. http://dx.doi.org/10.1177/1528083716670309.

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Lead-shielding products, such as lead aprons, are important materials for personal protection of physicians and patients from X-ray (gamma) radiation during medical operations. However, lead has environmental disadvantages such as high toxicity. The aim of this study was to manufacture an environmentally friendly and flexible textile-based radiation shielding material. In this work, 3/1 twill and some cellular woven fabrics were produced with conductive core yarns, and gamma radiation shielding effectiveness of these cellular woven fabrics were investigated and compared with that of the 3/1 tw
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3

HAKAN, ÖZDEMIR, and CAMGÖZ BERKAY. "The gamma radiation shielding effectiveness of textured steel yarn based fabrics." Industria Textila 69, no. 01 (2018): 44–49. http://dx.doi.org/10.35530/it.069.01.1347.

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Lead aprons that are lead-shielding products are generally used for personal protection of physicians and patients from X-ray (gamma) radiation during medical operations; lead has environmental disadvantages, with high toxicity, though. Therefore, the aim of this research was to produce an environmentally friendly and flexible textile-based radiation shielding material. In this work, 2/2 twill, 3/1 twill, Herringbone, Whipcord, which are twill derivatives, Barathea and Crêpe woven fabrics, which are sateen derivatives, woven with textured steel yarns, which have soft feeling and flexibility, a
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4

Faisal, Shafiqul Islam, and Abi Muttaquin Bin Jalal Bayar. "Gamma Shielding Experiment Simulation utilizing MCNPX Code." Journal of Engineering Science 12, no. 2 (2021): 11–21. http://dx.doi.org/10.3329/jes.v12i2.54627.

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Experimental investigation requires materials, radiation sources, and test arrangements with a high monetary financial plan. Furthermore, radiation exposure involves people during the experiment. On the contrary, the simulation technique for examining radiation interactions is radio-logically safer, less timeconsuming, cost-effective, and applicable for all desired radiation sources. Through 48.86 mCi 662 keV Caesium-137 gamma-ray source; shielding experiment as well as simulation of it with MCNPX were performed for three shielding materials Lead, Copper, and Aluminum. These materials were pla
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5

Saniye, T. "Investigation of the Mass Attenuation Coefficients, Effective Atomic Numbers and Electron Densities for Compounds of Painkiller." Journal of Biomedical Research & Environmental Sciences 2, no. 1 (2021): 034–37. http://dx.doi.org/10.37871/jbres1184.

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In this study the effects of gamma radiations with compounds are an important subject in the field of medicine, radiation shielding and radiation physics. With technological advances the using of radiation has increased in the medicine in the last century. The mass absorpsion coefficient (µ/ρ) is the fundamental a quantity characterizing gamma ray and is of major importance in radiation shielding. In this study, the mass absorption coefficient of painkillers named Ketoprofen, Flurbiprofen, Etodolac, Ibuprofen, Meloxicam, Diclofenac and Aspirin were calculated at energy range from 4.65 keV to 5
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6

Hadad, Kamal, Hosein Majidi, and Samira Sarshough. "Enhanced radiation shielding with galena concrete." Nuclear Technology and Radiation Protection 30, no. 1 (2015): 70–74. http://dx.doi.org/10.2298/ntrp1501070h.

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A new concrete, containing galena mineral, with enhanced shielding properties for gamma sources is developed. To achieve optimized shielding properties, ten types of galena concrete containing different mixing ratios and a reference normal concrete of 2300 kg/m3 density are studied experimentally and numerically using Monte Carlo and XCOM codes. For building galena concrete, in addition to the main composition, micro-silica and water, galena mineral (containing lead) were used. The built samples have high density of 4470 kg/m3 to 5623 kg/m3 and compressive strength of 628 kg/m2 to 685 kg/m2. T
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7

Aziz, Md Akhlak Bin, Md Faisal Rahman, and Md Mahidul Haque Prodhan. "Comparison of Lead, Copper and Aluminium as Gamma Radiation Shielding Material through Experimental Measurements and Simulation Using MCNP Version 4c." International Journal of Contemporary Research and Review 9, no. 08 (2018): 20193–206. http://dx.doi.org/10.15520/ijcrr/2018/9/08/584.

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The paper compares Lead, Copper and Aluminium as gamma radiation shielding material using both experimental and simulation techniques. Cs- 137 (662KeV), Na-22 (511KeV) and Na- 22(1274KeV) were used as gamma radiation sources and a sodium iodide (NaI) detector was used to detect the radiation. Variations were noted for detected gamma count rates by changing shielding material thickness. In the experimental approach, thickness was varied by placing sheets of a particular test material one by one. For simulation, Monte Carlo n- Particle (MCNP) code version 4c was used and the geometry of the whol
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8

Tabbakh, F., V. Babaee, and Z. Naghsh-Nezhad. "Carbohydrate based materials for gamma radiation shielding." Journal of Physics: Conference Series 611 (May 7, 2015): 012015. http://dx.doi.org/10.1088/1742-6596/611/1/012015.

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9

McDermott, Patrick N. "Radiation shielding for gamma stereotactic radiosurgery units." Journal of Applied Clinical Medical Physics 8, no. 3 (2007): 147–57. http://dx.doi.org/10.1120/jacmp.v8i3.2355.

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10

Kim, Jaewoo, Duckbong Seo, Byung Chul Lee, Young Soo Seo, and William H. Miller. "Nano-W Dispersed Gamma Radiation Shielding Materials." Advanced Engineering Materials 16, no. 9 (2014): 1083–89. http://dx.doi.org/10.1002/adem.201400127.

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11

Almatari, M. "Gamma radiation shielding properties of glasses within the TeO2-TiO2-ZnO system." Radiochimica Acta 107, no. 6 (2019): 517–22. http://dx.doi.org/10.1515/ract-2018-3058.

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Abstract Radiations are widely used in hospitals and health services in radiotherapy and molecular imaging using x-ray and gamma radiation which considered as the most penetrating radiations and very difficult to shield. In this study, the radiation shielding properties of different zinc oxide (ZnO) concentrations of the (95-x)TeO2-5TiO2-xZnO (x=5, 10, 15, 20, 25, 30 and 40 mol%) glass system was investigated to be introduced as a new transparency effective shielding material. In order to study shielding properties, mass attenuation coefficients in the energy range of 0.015–15 MeV photon energ
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12

Ali, Suha Ismail Ahmed, and Éva Lublóy. "Radiation shielding structures : Concepts, behaviour and the role of the heavy weight concrete as a shielding material - Rewiev." Concrete Structures 21 (2020): 24–30. http://dx.doi.org/10.32970/cs.2020.1.4.

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The construction of radiation shielding buildings still developed. Application of ionizing radiations became necessary for different reasons, like electricity generation, industry, medical (therapy treatment), agriculture, and scientific research. Different countries all over the world moving toward energy saving, besides growing the demand for using radiation in several aspects. Nuclear power plants, healthcare buildings, industrial buildings, and aerospace are the main neutrons and gamma shielding buildings. Special design and building materials are required to enhance safety and reduce the
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13

Haque, M. M., M. Shamsuzzaman, Muhammad Borhan Uddin, Abu Zafor Mohammad Salahuddin, and Ruhul A. Khan. "Fabrication and Characterization of Shielding Properties of Heavy Mineral Reinforced Polymer Composite Materials for Radiation Protection." European Journal of Engineering Research and Science 4, no. 3 (2019): 15–20. http://dx.doi.org/10.24018/ejers.2019.4.3.1132.

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Heavy mineral and unsaturated polyester resin (UPR) based composite blocks were prepared for potential shielding of ionizing radiations. Locally available heavy minerals with Ilmenite, Magnetite, Garnet, Rutile, Zirconium contents were used to fabricate the composite blocks for the gamma photons with energies 0.662 MeV - 1.25 MeV. The shielding capacity was evaluated in terms of Half Value Layer (HVL), Tenth Value Layer (TVL), Sixteenth Value Layer (SVL), Linear attenuation coefficient, Mass attenuation coefficient, and reduced % of radiation intensity. The Ilmenite composite exhibits relative
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14

Chen, Shuo, Mohamed Bourham, and Afsaneh Rabiei. "Novel light-weight materials for shielding gamma ray." Radiation Physics and Chemistry 96 (March 2014): 27–37. http://dx.doi.org/10.1016/j.radphyschem.2013.08.001.

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15

Şakar, Erdem, Mehmet Büyükyıldız, Bünyamin Alım, Betül Ceviz Şakar, and Murat Kurudirek. "Leaded brass alloys for gamma-ray shielding applications." Radiation Physics and Chemistry 159 (June 2019): 64–69. http://dx.doi.org/10.1016/j.radphyschem.2019.02.042.

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16

Alekseev, A. G., P. A. Alekseev, and A. A. Yanovich. "GAMMA SPECTROMETER FOR THE TESTING OF RADIATION SHIELDING." EurasianUnionScientists 1, no. 63 (2019): 8–13. http://dx.doi.org/10.31618/esu.2413-9335.2019.1.63.155.

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17

Sayyed, M. I., Kawa M. Kaky, Erdem Şakar, Uğur Akbaba, Malaa M. Taki, and O. Agar. "Gamma radiation shielding investigations for selected germanate glasses." Journal of Non-Crystalline Solids 512 (May 2019): 33–40. http://dx.doi.org/10.1016/j.jnoncrysol.2019.02.014.

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18

BİLGİCİ CENGİZ (EKER), Gülçin, İ̇lyas ÇAĞLAR, and Gökhan BİLİR. "GAMMA RADIATION SHIELDING PROPERTIES OF NATURAL GLASS OBSIDIAN." Eskişehir Technical University Journal of Science and Technology A - Applied Sciences and Engineering 21, no. 4 (2020): 539–53. http://dx.doi.org/10.18038/estubtda.755217.

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19

Calzada, Elbio, Florian Grünauer, Burkhard Schillinger, and Harald Türck. "Reusable shielding material for neutron- and gamma-radiation." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 651, no. 1 (2011): 77–80. http://dx.doi.org/10.1016/j.nima.2010.12.239.

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20

Gedik, S., and A. F. Baytaş. "Shielding of Gamma Radiation by Using Porous Materials." Acta Physica Polonica A 128, no. 2B (2015): B—174—B—176. http://dx.doi.org/10.12693/aphyspola.128.b-174.

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21

Garcia, FernandoMireles. "Design and construction of shielding for gamma radiation." International Journal of Radiation Applications and Instrumentation. Part C. Radiation Physics and Chemistry 33, no. 3 (1989): 291. http://dx.doi.org/10.1016/1359-0197(89)90210-5.

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22

Singh, Kanwaldeep, Sukhpal Singh, A. S. Dhaliwal, and Gurmel Singh. "Gamma radiation shielding analysis of lead-flyash concretes." Applied Radiation and Isotopes 95 (January 2015): 174–79. http://dx.doi.org/10.1016/j.apradiso.2014.10.022.

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23

Joshi, Shailesh, V. Snehalatha, K. Sivasubramanian, D. Ponraju, V. Jayaraman, and B. Venkatraman. "Radiation Stability of Epoxy-Based Gamma Shielding Material." Journal of Materials Engineering and Performance 28, no. 12 (2019): 7332–41. http://dx.doi.org/10.1007/s11665-019-04487-0.

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24

Meckbach, Reinhard, Peter Jacob, and Herwig G. Paretzke. "Shielding of gamma radiation by typical European houses." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 255, no. 1-2 (1987): 160–64. http://dx.doi.org/10.1016/0168-9002(87)91093-x.

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25

Chauhan, R. K., Manish Mudgal, Sarika Verma, S. S. Amritphale, Satyabrata Das, and Arvind Shrivastva. "Development and Design Mix of Radiation Shielding Concrete for Gamma-ray Shielding." Journal of Inorganic and Organometallic Polymers and Materials 27, no. 4 (2017): 871–82. http://dx.doi.org/10.1007/s10904-017-0531-y.

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26

Hussein, Khalid I., Mohammed S. Alqahtani, Iwona Grelowska, et al. "Optically transparent glass modified with metal oxides for X-rays and gamma rays shielding material." Journal of X-Ray Science and Technology 29, no. 2 (2021): 331–45. http://dx.doi.org/10.3233/xst-200780.

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BACKGROUND: Metal oxide glass composites have attracted huge interest as promising shielding materials to replace toxic, heavy, and costly conventional shielding materials. OBJECTIVE: In this work, we evaluate shielding effectiveness of four novel tellurite-based glasses samples doped with oxide metals (namely, A, B, C, and D, which are 75TeO2- 10P2O5- 10ZnO- 5PbF2- 0.24Er2O3 ; 70TeO2- 10P2O5- 10ZnO- 5PbF2 -5MgO- 0.24Er2O3; 70TeO2- 10P2O5- 10ZnO- 5PbF2- 5BaO- 0.24Er2O3 ; and 70TeO2- 10P2O5-10ZnO- 5PbF2- 5SrO; respectively) by assessing them through a wide range of ionizing radiation energies (
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27

Domański, Szymon, Michał A. Gryziński, Maciej Maciak, Łukasz Murawski, Piotr Tulik, and Katarzyna Tymińska. "Experimental investigation on radiation shielding of high performance concrete for nuclear and radiotherapy facilities." Polish Journal of Medical Physics and Engineering 22, no. 2 (2016): 41–47. http://dx.doi.org/10.1515/pjmpe-2016-0008.

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Abstract This paper presents the set of procedures developed in Radiation Protection Measurements Laboratory at National Centre for Nuclear Research for evaluation of shielding properties of high performance concrete. The purpose of such procedure is to characterize the material behaviour against gamma and neutron radiation. The range of the densities of the concrete specimens was from 2300 to 3900 kg/m3. The shielding properties against photons were evaluated using 137Cs and 60Co sources. The neutron radiation measurements have been performed by measuring the transmitted radiation from 239PuB
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28

Wu, Yin, Yi Cao, Ying Wu, and Dichen Li. "Mechanical Properties and Gamma-Ray Shielding Performance of 3D-Printed Poly-Ether-Ether-Ketone/Tungsten Composites." Materials 13, no. 20 (2020): 4475. http://dx.doi.org/10.3390/ma13204475.

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Nuclear energy provides enduring power to space vehicles, but special attention should be paid to radiation shielding during the development and use of nuclear energy systems. In this paper, novel composite materials containing poly-ether-ether-ketone (PEEK) as a substrate and different tungsten contents as a reinforcing agent were developed and tested as shielding for gamma-ray radiation. Shielding test bodies were quickly processed by fused deposition modeling (FDM) 3D printing, and their mechanical, shielding properties of composite materials were evaluated. The results revealed shielding m
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29

Ngoc, Le Van, and Trinh Dang Ha. "Monte-Carlo Determination of Dose Rates In Spherical Pressurized Water Reactor Shield." Communications in Physics 20, no. 1 (2010): 91. http://dx.doi.org/10.15625/0868-3166/20/1/2155.

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The nuclear reactor emits various kinds of nuclear radiations during operation. However, the main contributions to the radiation field in the reactor are given by neutrons and gamma rays. These radiation components are the principal concern of reactor shielding. In our study the neutron and gamma radiation dose rates at different depths in concrete bio-shield of the PWR were calculated based on spherical model for M-C simulation with using MCNP4C2. The simulation results were compared with the results obtained from calculations based on S$_{8}$P$_{3}$ spherical approximation with using the ANI
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30

Singh, Vishwaanath, and Nagappa Badiger. "Investigation on radiation shielding parameters of ordinary, heavy and super heavy concretes." Nuclear Technology and Radiation Protection 29, no. 2 (2014): 149–56. http://dx.doi.org/10.2298/ntrp1402149s.

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Shielding of a reactor is required for protection of people and environment during normal operation and accidental situations. In the present paper we investigated the shielding parameters viz. mass attenuation coefficients, linear attenuation coefficients, tenth-value layer, effective atomic numbers, kerma relative to air and exposure buildup factors for gamma-ray for ordinary, heavy, and super heavy concretes. Macroscopic effective removal cross-sections for fast neutron had also been calculated. Ordinary concrete is economically suitable for mixture high energy gamma-ray and neutron as it h
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31

Mollah, Abdus Sattar. "Evaluation of Gamma Radiation Attenuation Characteristics of Different Type Shielding Materials used in Nuclear Medicine Services." Bangladesh Journal of Nuclear Medicine 21, no. 2 (2019): 108–14. http://dx.doi.org/10.3329/bjnm.v21i2.40361.

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Gamma-ray radiation shielding properties such as linear attenuation coefficient (m), mass attenuation coefficient (m/r), half- value thickness (HVT), tenth value thickness (TVL) and mean free path (MFP) were calculated for different types of radiation absorbing materials such as Concrete, Aluminum, Iron, Copper, Lead, Lead-glass and Tungsten. These materials are being widely used as radiation shielding materials in different areas of nuclear medicine facilities for different purposes. The XCOM and in-house developed computer program were used to calculate the above mentioned parameters for gam
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32

Singh, Kulwant, Harvinder Singh, Gopi Sharma, et al. "Gamma-ray shielding properties of CaO–SrO–B2O3 glasses." Radiation Physics and Chemistry 72, no. 2-3 (2005): 225–28. http://dx.doi.org/10.1016/j.radphyschem.2003.11.010.

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33

Mann, Kulwinder Singh. "Investigation of gamma-ray shielding by double layered enclosures." Radiation Physics and Chemistry 159 (June 2019): 207–21. http://dx.doi.org/10.1016/j.radphyschem.2019.03.007.

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34

Ahmed, Bashir, G. B. Shah, Azhar H. Malik, Aurangzeb, and M. Rizwan. "Gamma-ray shielding characteristics of flexible silicone tungsten composites." Applied Radiation and Isotopes 155 (January 2020): 108901. http://dx.doi.org/10.1016/j.apradiso.2019.108901.

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35

Glumglomchit, Punsak, Juniastel Rajagukguk, Jakrapong Kaewkhao, and Keerati Kirdsiri. "A Novel Radiation Shielding Material for Gamma-Ray: The Development of Lutetium Lithium Borate Glasses." Key Engineering Materials 766 (April 2018): 246–51. http://dx.doi.org/10.4028/www.scientific.net/kem.766.246.

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This work, gamma-ray shielding properties of the lutetium lithium borate glasses in the system Lu2O3 - Li2O - B2O3 have been evaluated as a shielding material at 662 keV photon energy. While the experimental mass attenuation coefficients (μm) have been determined by using the narrow beam transmission method, the theoretical data were calculated using WinXCom program. The good agreements between experimental and theoretical values have been obtained. Both experimental and computational mass attenuation coefficients data were used to obtain the effective atomic number (Zeff), and the effective e
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36

Almohiy, H., M. Saad, Y. M. AbouDeif, et al. "Improvement of Gamma Radiation Shielding Features for Fluorophosphate Glasses Doping with Sm2O3 (PZBKNA)." Journal of Nanoelectronics and Optoelectronics 15, no. 11 (2020): 1374–80. http://dx.doi.org/10.1166/jno.2020.2858.

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This research reported on the radiation safety characteristics of doped fluorophosphate glasses with heavy rare earth lanthanide (Sm2O3) in the composition 40P2O5/30ZnO/20BaF2/3.8K2TeO3/1.2Al2O3/5.0Nb2O5/30000 ppm Sm2O3 and 40P2O5/30ZnO/20BaF2/3.8K2TeO3/1.2Al2O3/5.0Nb2O5/40000 ppm Sm2O3 in mol%. The parameters for shielding like that mass attenuation coefficient, MAC, linear attenuation coefficient, LAC, tenth value layers, TVL, half-value layers, HVL, effective atomic number, (Zeff), mean free path, MFP, electron density, Neff, electronic cross-sections, ECS, and total atomic cross-sections,
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37

Tran, Thanh Thien, Tao Van Chau, Tam Duc Hoang, and Yen Thi Hong Vo. "STUDY ON THE EFFECT OF NATURAL BACKGROUND FOR GAMMA SPECTROMETER SYSTEM." Science and Technology Development Journal 14, no. 4 (2011): 16–23. http://dx.doi.org/10.32508/stdj.v14i4.2032.

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In the analysis of environmental radioactive isotopes using gamma spectrometry, natural background radiation is an important parameter related to the analytical results directly. Therefore, in this work, the influence of natural background radiation was studied for two models: with and without shielding of gamma spectrometer system. The initial results showed that the minimum detectable activity (MDA) of radionuclides such as 234Th, 226Ra, 212Pb, 208Tl, 40K, 214Pb, 214Bi, 228Ac have the difference of two models from 10% to 503%. This is the basis for researches to improve the lead shielding ch
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38

ALMisned, Ghada, F. Akman, Waheed S. AbuShanab, et al. "Novel Cu/Zn Reinforced Polymer Composites: Experimental Characterization for Radiation Protection Efficiency (RPE) and Shielding Properties for Alpha, Proton, Neutron, and Gamma Radiations." Polymers 13, no. 18 (2021): 3157. http://dx.doi.org/10.3390/polym13183157.

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In this study, brass (Cu/Zn) reinforced polymer composites with different proportions of brass powders were fabricated. Different types of nuclear shielding parameters such as mass and linear attenuation coefficients, radiation protection efficiency, half and tenth value layers, and effective atomic number values were determined experimentally and theoretically in the energy range of 0.060–1.408 MeV in terms of gamma-ray shielding capabilities of fabricated polymer composites. A high Purity Germanium detector (HPGe) in conjunction with a Multi-Channel Analyzer (MCA) and twenty-two characterist
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39

Madiba, I. G., A. Braun, N. Émond, et al. "Resonant photoemission spectroscopy of gamma irradiated VO2 films." MRS Advances 3, no. 42-43 (2018): 2499–503. http://dx.doi.org/10.1557/adv.2018.356.

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AbstractVanadium dioxide thin films are considered as smart functional coatings for thermal shielding, and are attractive as a passive thermal shield for spacecrafts. In space they would, however, be subjected to bombardment by interstellar dust particles and electromagnetic radiation. Materials subjected to irradiation will suffer damages induced by the displacement cascades initiated by nuclear reaction. Such cosmic radiation can severely impact the structure and function of materials. To study this effect in the laboratory, we have deposited VO2 films on silicon wafers and exposed them to γ
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40

Singh, Ravinder, Sukhpal Singh, Gurmel Singh, and Kulwant Singh Thind. "Gamma Radiation Shielding Properties of Steel and Iron Slags." New Journal of Glass and Ceramics 07, no. 01 (2017): 1–11. http://dx.doi.org/10.4236/njgc.2017.71001.

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41

Oto, Berna, Nergiz Yıldız, Fatma Akdemir, and Esra Kavaz. "Investigation of gamma radiation shielding properties of various ores." Progress in Nuclear Energy 85 (November 2015): 391–403. http://dx.doi.org/10.1016/j.pnucene.2015.07.016.

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42

Kaewjaeng, S., S. Kothan, N. Chanthima, H. J. Kim, and J. Kaewkhao. "Gamma radiation shielding materials of lanthanum calcium silicoborate glasses." Materials Today: Proceedings 5, no. 7 (2018): 14901–6. http://dx.doi.org/10.1016/j.matpr.2018.04.027.

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43

Çağlar, İlyas, Gülçin Bilgici Cengiz, and Gökhan Bilir. "Gamma Radiation Shielding Properties of Some Binary Tellurite Glasses." Journal of Non-Crystalline Solids 574 (December 2021): 121139. http://dx.doi.org/10.1016/j.jnoncrysol.2021.121139.

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44

Bhosale, Rameshwar, Chaitali More, Dhammajyot Gaikwad, Pravina Pawar, and Madhav Rode. "Radiation shielding and gamma ray attenuation properties of some polymers." Nuclear Technology and Radiation Protection 32, no. 3 (2017): 288–93. http://dx.doi.org/10.2298/ntrp1703288b.

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In the present work we investigated the gamma radiation parameters as mass attenuation coefficients ?/?, the total atomic scattering cross-sections ??, the electronic scattering cross-sections se, the effective atomic numbers Zeff, and the effective electron densities Neff for some polymers such as polyoxymethylene (CH2O), poly acrylonitrile (C3H3N), natural rubber (C5H8), poly ethyl acrylate (C5H8O2), polyphenyl methacrylate (C10H10O2), and polyethylene tetraphthalate (C10H8O4). The gamma ray photons were detected by NaI(Tl) detector with resolution of 8.2 % at 662 keV, using radioactive gamm
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45

Huang, Furong, Yimeng Wang, Peiyu Wang, et al. "Oxidized multiwall carbon nanotube/silicone foam composites with effective electromagnetic interference shielding and high gamma radiation stability." RSC Advances 8, no. 43 (2018): 24236–42. http://dx.doi.org/10.1039/c8ra03314e.

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46

Talley, Samantha J., Tom Robison, Alexander M. Long, et al. "Flexible 3D printed silicones for gamma and neutron radiation shielding." Radiation Physics and Chemistry 188 (November 2021): 109616. http://dx.doi.org/10.1016/j.radphyschem.2021.109616.

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47

Akkurt, Iskender, Sabiha Anas Boussaa, and Kadir Gunoglu. "Calculation of Linear Attenuation Coefficients of Algerian Silica Sand (ASS)." Advanced Science, Engineering and Medicine 12, no. 10 (2020): 1300–1302. http://dx.doi.org/10.1166/asem.2020.2706.

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Radiation is an important phoneme and thus radiation shielding is one of the most popular subjects for researchers. Sand is the main materials to produce besides many things also construction materials. It may also be used as a decorative material and therefore it is important to know its radiation shielding parameters. In this study, linear attenuation coefficients of Algerian Silica Sand (ASS) were calculated using computer code of XCOM for 1 keV—100 GeV gamma energies.
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48

Temir, A., K. Sh Zhumadilov, A. Kozlovskiy, A. Smagulova, D. I. Shlimas, and A. V. Trukhanov. "Study of gamma radiation shielding efficiency by 0.5TeO2-(0.5-x)Bi2O3-xWO3 glasses." Eurasian Journal of Physics and Functional Materials 5, no. 2 (2021): 126–32. http://dx.doi.org/10.32523/ejpfm.2021050205.

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Abstract:
This article is devoted to the study of determination of gamma radiation shielding efficiency by new radiation-resistant glasses of the 0.5TeO2-(0.5-x)Bi2O3-xWO3 type. As a method of obtaining glasses, the method of solid-phase synthesis combined with thermal annealing and subsequent hardening was used. The amorphous nature of the synthesized samples was confirmed by X-ray phase analysis. Determination of the shielding efficiency, as well as the effect of Bi2O3 and WO3 content in the glass composition on the attenuation efficiency was carried out by evaluation of gamma radiation intensities fr
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49

Singh, D., G. S. Mudahar, K. S. Thind, and Hardev Singh Virk. "Structural Investigations of Gamma-Irradiated PbO Glasses." Solid State Phenomena 239 (August 2015): 98–109. http://dx.doi.org/10.4028/www.scientific.net/ssp.239.98.

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The effects of gamma radiations on the optical, physical and structural properties of zinc lead borate xZnO-2xPbO-(1-3x)B2O3 and zinc lead borosilicate xZnO-2xPbO-1/2(1-3x)B2O3-1/2(1-3x)SiO2 glasses have been investigated. Differential Scanning Calorimetry (DSC), Ultraviolet-Visible (UV-Vis) and Fourier Transmission Infra-red (FTIR) spectroscopic techniques have been used to compare the properties of samples before and after gamma irradiation by a dose of 2.5 kGy. The variation of density, optical band gap (Eg), IR absorption bands and glass transition temperature (Tg) indicates that the struc
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50

Wu, You, Quan-Ping Zhang, Dong Zhou, et al. "One-dimensional lead borate nanowhiskers for the joint shielding of neutron and gamma radiation: controlled synthesis, microstructure, and performance evaluation." CrystEngComm 19, no. 48 (2017): 7260–69. http://dx.doi.org/10.1039/c7ce01547j.

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