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Journal articles on the topic 'Shielding (Radiation) – Evaluation'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 February 2022

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1

Cho, Yong-In, Chang-Soo Kim, and Jung-Hoon Kim. "Evaluation of syringe shield effectiveness in handling radiopharmaceuticals." Nuclear Technology and Radiation Protection 30, no. 2 (2015): 158–63. http://dx.doi.org/10.2298/ntrp1502158c.

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The purpose of this study was to evaluate the effectiveness of the radiation shield of radionuclide syringes and the personal dose equivalent by performing a simulation of radionuclides used in nuclear medicine diagnosis. In order to evaluate the dose depending on the distance between the radiation source and the ICRU sphere against the thickness of the shielding device, the distance at which a nuclear medicine worker may inadvertently come into contact with radiation from the radiation source was set at 0 cm to 30 cm according to the thickness of the shield, thus fixing the ICRU sphere. For a dose evaluation, Hp(10), Hp(3), and Hp(0.07) measurable in specific depth of the ICRU were evaluated. It was found that a dose measured on skin surface of nuclear medicine workers was relatively higher, that the dose varied in relation to the thickness of the radiation shield, and that the shielding effect decreased for some radiation sources such as 67Ga and 111In. It proved necessary to increase thickness of shielding device to the radiation sources such as 67Ga and 111In. It is also considered that a study of proper shielding thickness will be needed in future.

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2

CHIDA, KOICHI, YOSHIAKI MORISHIMA, YOSHIAKI KATAHIRA, HIROO CHIBA, and MASAYUKI ZUGUCHI. "Evaluation of Additional Lead Shielding in Protecting the Physician from Radiation during Cardiac Interventional Procedures." Japanese Journal of Radiological Technology 61, no. 12 (2005): 1632–37. http://dx.doi.org/10.6009/jjrt.kj00004022974.

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3

Sayyed, Mohammed I., Ferdi Akman, Veysel Turan, and Aslı Araz. "Evaluation of radiation absorption capacity of some soil samples." Radiochimica Acta 107, no. 1 (December 19, 2018): 83–93. http://dx.doi.org/10.1515/ract-2018-2996.

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Abstract The aim of the present work is to investigate the radiation absorption capacity of different soil samples in Turkey. For this purpose, we used a γ ray transmission geometry to measure the mass attenuation coefficients of eight soil samples collected between Bingöl city and Solhan district, Turkey at different γ-ray energies in the range of 13.94–88.04 keV. The radioactive sources utilized in the experiment were 241Am, 109Cd and 133Ba. FFAST and WinXCOM programs were used to evaluate the theoretical mass attenuation coefficients values of the selected soil samples. There is a good agreement between experimental and theoretical results. Additionally, the mass attenuation coefficients values used to evaluate different radiation shielding parameters such as effective atomic number, half value layer and mean free path. The variation of shielding parameters was examined for soil composition and photon energy. The obtained results revealed that S6 soil sample is the best soil in terms of shielding effectiveness among all the collected soils due to lower values for half value layer and mean free path. The effective removal cross-section (ΣR) of fast neutrons for the collected soils was also computed to examine neutrons shielding properties of the soil samples. It is found that the ΣR values for the soil samples are almost constant and lie within the range (0.04286–0.04949 cm−1).

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4

Krayushkin, V. V., P. A. Orlenko, and A. V. Larichev. "Technicoeconomic evaluation of radiation shielding for commercial electron accelerators." Soviet Atomic Energy 61, no. 3 (September 1986): 758–61. http://dx.doi.org/10.1007/bf01129883.

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5

Xu, Yun-Chuan, Quan-Ping Zhang, Jun-Hua Liu, You Wu, Li-Ping Liu, Dui-Gong Xu, and Yuan-Lin Zhou. "PbWO4 nanofibers for shielding gamma radiation: crystal growth, morphology and performance evaluation." CrystEngComm 20, no. 40 (2018): 6197–206. http://dx.doi.org/10.1039/c8ce01224e.

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6

Endo, A., and T. Sato. "Radiation transport calculations for cosmic radiation." Annals of the ICRP 41, no. 3-4 (October 2012): 142–53. http://dx.doi.org/10.1016/j.icrp.2012.06.010.

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The radiation environment inside and near spacecraft consists of various components of primary radiation in space and secondary radiation produced by the interaction of the primary radiation with the walls and equipment of the spacecraft. Radiation fields inside astronauts are different from those outside them, because of the body's self-shielding as well as the nuclear fragmentation reactions occurring in the human body. Several computer codes have been developed to simulate the physical processes of the coupled transport of protons, high-charge and high-energy nuclei, and the secondary radiation produced in atomic and nuclear collision processes in matter. These computer codes have been used in various space radiation protection applications: shielding design for spacecraft and planetary habitats, simulation of instrument and detector responses, analysis of absorbed doses and quality factors in organs and tissues, and study of biological effects. This paper focuses on the methods and computer codes used for radiation transport calculations on cosmic radiation, and their application to the analysis of radiation fields inside spacecraft, evaluation of organ doses in the human body, and calculation of dose conversion coefficients using the reference phantoms defined in ICRP Publication 110.

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7

Hossain, MN, MS Mia, TA Biman, H. Mehdi, and F. Begum. "Evaluation of the shielding parameters implemented in the PET-CT facility at the National Institute of Nuclear Medicine & Allied Sciences (NINMAS), Dhaka." Bangladesh Journal of Physics 26, no. 2 (September 20, 2020): 51–59. http://dx.doi.org/10.3329/bjphy.v26i2.49306.

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Positron Emission Tomography (PET) combined with Computed Tomography (CT) is a very sensitive diagnostic imaging modality that consists of both functional and anatomical imaging into one combined scanning system. Because of the high energy of annihilation radiation (511 keV) for PET tracers, shielding requirements are an important consideration in the design of a PET/CT facility. The shielding evaluation for adequate radiation protection of a PET/CT facility consists of the assessment of annual effective dose both to occupational workers and to members of the public’s. The overall shielding assessment takes into account the radionuclides activity involved, the facility design, the scanning procedures, the expected number of patients per year and so on. The evaluation also depends upon the size of the PET/CT imaging room and patient’s uptake rooms, the thickness and the physical materials of walls, floors and ceilings. In this work we verified the adequacy of shielding installed in the PET/CT facility at the National Institute of Nuclear Medicine & Allied Sciences (NINMAS), Dhaka. The assessment results were compared to the provided shielding which was the design requirements. Bangladesh Journal of Physics, 26(2), 51-59, December 2019

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8

YOSHIKAWA, Ema, Hideo KOMINE, Shigeru GOTO, Mitsugu YOSHIMURA, Akihiko SUZUKI, Seiichi NARUSHIMA, Yasunori ARAI, Shinsuke UJIIE, Yuki SAKODA, and Yasushi NAGAE. "THE QUANTITATIVE EVALUATION FOR RADIATION SHIELDING CAPABILITIES OF SOIL MATERIALS." Journal of Japan Society of Civil Engineers, Ser. C (Geosphere Engineering) 73, no. 4 (2017): 342–54. http://dx.doi.org/10.2208/jscejge.73.342.

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9

Saudi, H. A., and Ei-Said H. Ei-Mosallamy. "Evaluation of Polymethyl Methacrylate Sheets as a Radiation Shielding Material." Journal of Packaging Technology and Research 4, no. 3 (August 27, 2020): 227–33. http://dx.doi.org/10.1007/s41783-020-00098-6.

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10

Pomaro, B., V. A. Salomoni, F. Gramegna, G. Prete, and C. E. Majorana. "Radiation damage evaluation on concrete shielding for nuclear physics experiments." Annals of Solid and Structural Mechanics 2, no. 2-4 (November 3, 2011): 123–42. http://dx.doi.org/10.1007/s12356-011-0023-7.

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11

An, YoungHwa, Changrae Seon, MunSeong Cheon, Sunil Pak, Jihyun Choi, Hyeon Gon Lee, Philippe Bernascolle, et al. "Radiation shielding design evaluation for ITER VUV edge imaging spectrometer." Fusion Engineering and Design 123 (November 2017): 787–92. http://dx.doi.org/10.1016/j.fusengdes.2017.04.096.

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12

Panova, O. V., G. Iu Krasnianskyi, and I. O. Aznaurian. "Evaluation of electromagnetic radiation shielding characteristics of facing building vaterials." IOP Conference Series: Materials Science and Engineering 1164, no. 1 (June 1, 2021): 012057. http://dx.doi.org/10.1088/1757-899x/1164/1/012057.

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13

Viswanathan, S., S. Chandrasekaran, and B. Venkatraman. "Nondestructive Evaluation of Hot Cell Liner Bricks by Radiometric Testing." Materials Evaluation 79, no. 2 (February 1, 2021): 106–12. http://dx.doi.org/10.32548/2021.me-04118.

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In nuclear facilities, controlling radiation exposure to operating personnel within limits specified by the regulatory body is mandatory; it is required to maintain the radiation level in occupancy areas “as low as reasonably achievable” (ALARA). Highly radioactive sources, materials, and components are enclosed in concrete cells, known as hot cells. Masterslave manipulators (MSMs) are used for the remote handling of equipment located in the hot cell. The MSM is fitted into the hot cell with liner bricks made of lead. The liner brick assembly is a lead poured structure with a steel lining, which gives an effective longitudinal shielding thickness of 250 mm when fitted into the cell with the MSM. Conventional nondestructive testing (NDT) methods such as radiographic testing (RT) and ultrasonic testing have limitations with respect to thickness and coarse-grained structures. Gamma radiometry, which is based on the principle of differential attenuation of radiation, has been developed and adopted in similar applications (Suresh Kumar et al. 2011). It is a challenge to optimize the gamma source strength required for testing, taking into account the sensitivity of the radiation detector and shielding thickness of the component under testing. This paper focuses on the choice of the radiation source and its strength, the experimental approach, the theoretical modeling undertaken for dose-rate estimation, and the actual measurement of radiation during the radiometric testing of MSM liner bricks.

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14

Kharita, M. H., M. Takeyeddin, M. Alnassar, and S. Yousef. "Development of special radiation shielding concretes using natural local materials and evaluation of their shielding characteristics." Progress in Nuclear Energy 50, no. 1 (January 2008): 33–36. http://dx.doi.org/10.1016/j.pnucene.2007.10.004.

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15

Ertel, Andrew, Jeffrey Nadelson, Adhir R. Shroff, Ranya Sweis, Dean Ferrera, and Mladen I. Vidovich. "Radiation Dose Reduction during Radial Cardiac Catheterization: Evaluation of a Dedicated Radial Angiography Absorption Shielding Drape." ISRN Cardiology 2012 (September 4, 2012): 1–5. http://dx.doi.org/10.5402/2012/769167.

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Objectives. Radiation scatter protection shield drapes have been designed with the goal of decreasing radiation dose to the operators during transfemoral catheterization. We sought to investigate the impact on operator radiation exposure of various shielding drapes specifically designed for the radial approach. Background. Radial access for cardiac catheterization has increased due to improved patient comfort and decreased bleeding complications. There are concerns for increased radiation exposure to patients and operators. Methods. Radiation doses to a simulated operator were measured with a RadCal Dosimeter in the cardiac catheterization laboratory. The mock patient was a 97.5 kg fission product phantom. Three lead-free drape designs were studied. The drapes were placed just proximal to the right wrist and extended medially to phantom’s trunk. Simulated diagnostic coronary angiography included 6 minutes of fluoroscopy time and 32 seconds of cineangiography time at 4 standard angulated views (8 s each), both 15 frames/s. ANOVA with Bonferroni correction was used for statistical analysis. Results. All drape designs led to substantial reductions in operator radiation exposure compared to control (P<0.0001). The greatest decrease in radiation exposure (72%) was with the L-shaped design. Conclusions. Dedicated radial shielding drapes decrease radiation exposure to the operator by up to 72% during simulated cardiac catheterization.

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16

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 (June 22, 2021): 126–32. http://dx.doi.org/10.32523/ejpfm.2021050205.

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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 from the 137Cs source, with a gamma ray energy of 661 keV. The evaluation was performed on parameters such as radiation protection efficiency, linear and mass attenuation coefficients, half-value layer and mean free path. During the studies, it was found that glasses of the following composition 0.5TeO2-0.1Bi2O3-0.4WO3 are most effective, which are 1.3-2 times higher than those of the composition 0.5TeO2-0.4Bi2O3-0.1WO3.

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17

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 (August 5, 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 gamma-ray energies of 100 keV, 200 keV and 511 keV. The gamma-ray energy range used in nuclear medicine is between 100 keV and 511 keV. Results show that attenuation coefficient decreases with increase of gamma-ray energy, and attenuation coefficient increases with increase of density and shows significant variation for different materials. Linear attenuation coefficient depends on the energy of incident gamma-rays and the nature of the absorbing materials. These gamma-ray attenuation parameters of different absorbing materials can be used for proper shielding design of syringe shield, isotope storage container, isotope transport container, personnel protective shield barrier, radioactive waste storage facility etc. in nuclear medicine services. Bangladesh J. Nuclear Med. 21(2): 108-114, July 2018

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18

Han, Sang-Hyun, Beom-Heui Han, Sang-Ho Lee, Dong-Heui Hong, and Gi-Jin Kim. "Evaluation of Radiation Shielding Rate of Lead Aprons in Nuclear Medicine." Journal of Radiological Science and Technology 40, no. 1 (March 31, 2017): 41–47. http://dx.doi.org/10.17946/jrst.2017.40.1.07.

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19

Bon-Yeoul, Koo, and Han Sang-Hyun. "A Study on the Performance Evaluation of Portable Radiation Shielding Apparatus." Journal of Radiological Science and Technology 41, no. 4 (August 30, 2018): 289–95. http://dx.doi.org/10.17946/jrst.2018.41.4.289.

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20

Wang, Jinjun, Guofeng Li, and Dechuan Meng. "Evaluation of the performance of peridotite aggregates for radiation shielding concrete." Annals of Nuclear Energy 71 (September 2014): 436–39. http://dx.doi.org/10.1016/j.anucene.2014.04.012.

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21

Rammah, Y. S., I. O. Olarinoye, F. I. El-Agawany, K. A. Mahmoud, Iskender Akkurt, and ElSayed Yousef. "Evaluation of radiation shielding capacity of vanadium–tellurite–antimonite semiconducting glasses." Optical Materials 114 (April 2021): 110897. http://dx.doi.org/10.1016/j.optmat.2021.110897.

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22

Fang, Sheng, Jianzhu Cao, Wenqian Li, Chen Luo, Feng Yao, Xiaofan Li, and Kai Li. "Shielding Design and Dose Evaluation for HTR-PM Fuel Transport Pipelines by QAD-CGA Program." Science and Technology of Nuclear Installations 2021 (May 3, 2021): 1–6. http://dx.doi.org/10.1155/2021/6686919.

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The spherical fuel elements are adopted in the high-temperature gas-cooled reactor pebble-module (HTR-PM). The fuel elements will be discharged continuously from the reactor core and transported into the fuel transport pipelines during the reactor operation, leading to spatially varying dose outside the pipeline. In this case, the dose evaluation faces two major challenges, including dynamic source terms and pipelines with varying lengths and shapes. This study tries to handle these challenges for HTR-PM through comprehensive calculations using the QAD-CGA program and to design the corresponding shielding of the pipeline. During the calculation, it is assumed that a spherical fuel element stays in different positions of the pipelines in turn, and the corresponding dose contributions were calculated. By integrating the dose contributions at different positions, the dose at the points of interest can be obtained. The total dose is further determined according to the assumed fuel elements transport speed of 5 m/s and total 6000 fuel elements transportation per day. Two types of fuel transport pipelines and two source terms were considered, i.e., the spent fuel element transport pipelines with corresponding spent fuel source term and the different burn-up fuel element transport pipelines with the average burn-up fuel source term. Doses at different points of interest were calculated with no shielding scenario and with lead shielding of different thicknesses scenario. To evaluate the shielding effect, the dose limit of the orange radiation zone of HTR-PM and the radiation damage thresholds from NCRP report No.51 were both adopted. The calculated results show that, for pipelines that transport the spent fuel, a 4 cm lead shielding will be enough. And for pipelines that transport fuel elements with different burn-up, a 5 cm lead shielding will be added. The method and results can provide valuable reference for other work of HTR-PM.

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23

Yadav, Ashwani Kumar, Basilia Quispe Huillcara, Pablo Víctor Cerón Ramírez, Modesto Antonio Sosa Aquino, and Miguel Ángel Vallejo Hernández. "Structural Shielding Design of CT Facility using Monte Carlo Simulation." Journal of Nuclear Physics, Material Sciences, Radiation and Applications 8, no. 2 (February 10, 2021): 143–47. http://dx.doi.org/10.15415/jnp.2021.82018.

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Radiation application in medicine offers extraordinary benefits. But radiation is like a double-edged sword, it has both benefits and associated risks on the community in contact. To justify the safety of workers and members of the public, regulated use of radiation is assessed by the radiation protection protocols. The aim of this study is to design a Computed Tomography (CT) facility with a simplified model of CT scanner, whose shielding follows the guidelines of National Council on Radiation Protection and Measurements (NCRP) Report No. 147. To design the study model, Monte Carlo (MC) radiation transport code in MCNPX 2.6.0 was used for the simulation. Furthermore, MCNPX was used to measure the photon flux in a vicinity or the detector cell. To validate the functioning of the X-ray tube, the experimental results were compared with the X-ray Transition Energies Database of National Institute of Standards and Technology, U.S. Department of Commerce. The results obtained were within 0.60% of relative error. To confirm the functioning of shielding design, radiation protection quantity, air kerma was measured at several points outside, and inside of the CT room and they were under the radiation dose recommended by NCRP, which demonstrates that the shielding design wassuccessful in blocking the radiation. The study can be used for an easy evaluation of any CT room within the framework of the model of the study.

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24

Hao, Feiran, Wei Zhou, and Yue Gao. "Recent advances in nuclear radiation protective clothing materials." Materials Express 11, no. 8 (August 1, 2021): 1255–68. http://dx.doi.org/10.1166/mex.2021.1922.

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With the development of science and technology, the opportunities for military forces and general citizens to be exposed to a radioactive environment have greatly increased. It is urgent to establish a mature nuclear, biological and chemical protection system, of which nuclear radiation protective clothing is a vital part. Radiation protective clothing is clothing that ensures the protection of people in a radioactive environment by reducing the radiation exposure dose. Owing to the advances in material science, it is possible to develop radiation protective clothing with better performance. In this review, we focus on X-ray, γ-ray and thermal neutron shielding and elaborate on the following 3 aspects by citing a variety of examples: methods for measuring the shielding performance of radiation protective clothing, radiation protective clothing materials and the prospects and existing problems. In addition, a number of commercial nuclear radiation protective clothing is introduced, and their evaluation is expounded to explain the problems.

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25

Wu, You, Quan-Ping Zhang, Dong Zhou, Li-Ping Liu, Yun-Chuan Xu, Dui-Gong Xu, and Yuan-Lin Zhou. "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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26

Hirano, Teruyoshi O., Yhuki Katakami, Satoru Hashimoto, Ichiro Hatsumura, Tsukuru Nishitsunoi, Yaoki Yamashita, and Yasuyuki Mori. "Evaluation of the Durability of a Nuclear Bomb Shelter Made with Anti-Sievert® Concrete." MRS Advances 3, no. 51 (2018): 3061–67. http://dx.doi.org/10.1557/adv.2018.507.

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ABSTRACTWe have developed Anti- Sievert® concrete, which is a concrete reinforced shielding function as a building material that shields the influence from radioactive materials and its radiation. Cement, water, aggregate, sand material, Anti- Sievert® # 210, Anti- Sievert® # 216 formulation was optimized as those materials constituting Anti- Sievert® concrete. As a result, we realized shielding concrete with high fluidity to realize construction suitability by concrete pump[1]. Anti- Sievert® concrete has a shielding function of about 3 times as compared with ordinary concrete with respect to X ray (100 kV), and shows strength of more than 50 N/mm2. The durability characteristics against nuclear explosion using Anti-Sievert® concrete were simulated and reported in this paper.

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27

Lin, Ting An, Yu-Chun Chuang, Jan-Yi Lin, Mei-Chen Lin, Ching-Wen Lou, Keng Siang Sim, and Jia-Horng Lin. "Shielding-benefit Evaluation of Electromagnetic Radiation and UV Radiation for Multifunctional Composite Polypropylene Woven Fabrics." Fibers and Polymers 21, no. 10 (October 2020): 2380–88. http://dx.doi.org/10.1007/s12221-020-3140-2.

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28

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 (June 1, 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 239PuBe source. Scattered neutron radiation has been evaluated using the shadow cone technique. A set up of ionization chambers was used during all experiments. The gamma dose was measured using C-CO2 ionization chamber. The neutron dose was evaluated with recombination chamber of REM-2 type with appropriate recombination method applied. The method to distinguish gamma and neutron absorbed dose components in mixed radiation fields using twin detector method was presented. Also, recombination microdosimetric method was applied for the obtained results. Procedures to establish consecutive half value layers and tenth value layers (HVL and TVL) for gamma and neutron radiation were presented. Measured HVL and TVL values were linked with concrete density to highlight well known dependence. Also, influence of specific admixtures to concrete on neutron attenuation properties was studied. The results confirmed the feasibility of approach for the radiation shielding investigations.

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Albarzan, Badriah, Mohamed Y. Hanfi, Aljawhara H. Almuqrin, M. I. Sayyed, Haneen M. Alsafi, and K. A. Mahmoud. "The Influence of Titanium Dioxide on Silicate-Based Glasses: An Evaluation of the Mechanical and Radiation Shielding Properties." Materials 14, no. 12 (June 20, 2021): 3414. http://dx.doi.org/10.3390/ma14123414.

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The mechanical and radiation shielding features were reported for a quaternary Na2O-CaO-SiO2-TiO2 glass system used in radiation protection. The fundamentals of the Makishima–Mazinize model were applied to evaluate the elastic moduli of the glass samples. The elastic moduli, dissociation energy, and packing density increased as TiO2 increased. The glasses’ dissociation energy increased from 62.82 to 65.33 kJ/cm3, while the packing factor slightly increased between 12.97 and 13.00 as the TiO2 content increased. The MCNP-5 code was used to evaluate the gamma-ray shielding properties. The best linear attenuation coefficient was achieved for glass samples with a TiO2 content of 9 mol%: the coefficient decreased from 5.20 to 0.14 cm−1 as the photon energy increased from 0.015 to 15 MeV.

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30

Singh, Vishwanath P., N. M. Badiger, N. Chanthima, and J. Kaewkhao. "Evaluation of gamma-ray exposure buildup factors and neutron shielding for bismuth borosilicate glasses." Radiation Physics and Chemistry 98 (May 2014): 14–21. http://dx.doi.org/10.1016/j.radphyschem.2013.12.029.

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31

Kaur, Taranjot, Jeewan Sharma, and Tejbir Singh. "Experimental evaluation of gamma rays shielding parameters for Zn-Cd-Sn-Pb quaternary alloy." Radiation Physics and Chemistry 156 (March 2019): 193–98. http://dx.doi.org/10.1016/j.radphyschem.2018.11.010.

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32

Jacob, P., and R. Meckbach (INVITED). "Shielding Factors and External Dose Evaluation." Radiation Protection Dosimetry 21, no. 1-3 (November 1, 1987): 79–85. http://dx.doi.org/10.1093/rpd/21.1-3.79.

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33

Jacob, P., and R. Meckbach (INVITED). "Shielding Factors and External Dose Evaluation." Radiation Protection Dosimetry 21, no. 1-3 (November 1, 1987): 79–85. http://dx.doi.org/10.1093/oxfordjournals.rpd.a080057.

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34

Salhani, D., K. Ash, M. Soubra, and A. Laewen. "Evaluation of a commercial shielding block cutting system." International Journal of Radiation Oncology*Biology*Physics 30 (January 1994): 327. http://dx.doi.org/10.1016/0360-3016(94)90921-0.

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35

Nafea Arbilei, Marwan, and Jamal Mohammed Hamed. "EVALUATION OF X-RAY RADIATION SHIELDING OF CONCRETE WITH TWO POLYMERIC ADDITIVES." Journal of Engineering and Sustainable Development 23, no. 06 (November 1, 2019): 101–8. http://dx.doi.org/10.31272/jeasd.23.6.8.

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36

Ji, Young-Yong, Kyung-Kil Kwak, Dae-Seok Hong, and Jong-Sik Shon. "An Evaluation on the Radiation Shielding of the Radwaste Drum Assay Facility." Journal of the Korean Radioactive Waste Society 10, no. 2 (June 30, 2012): 117–23. http://dx.doi.org/10.7733/jkrws.2012.10.2.117.

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37

鲁, 维. "Evaluation of Space-Radiation-Spectrum Isotropy after Shielding Using Shannon Entropy Method." Journal of Aerospace Science and Technology 08, no. 04 (2020): 93–101. http://dx.doi.org/10.12677/jast.2020.84012.

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38

Plukis, A. "Evaluation of radiation shielding of RBMK-1500 reactor spent nuclear fuel containers." Lithuanian Journal of Physics 46, no. 3 (2006): 367–74. http://dx.doi.org/10.3952/lithjphys.46309.

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Han, Ki-tek, Sang Mook Kang, Jeho Min, and Han Ki Jang. "Characteristic Analysis of Concrete for Radiation Shielding Evaluation of Gamma Irradiation Facilities." EPJ Web of Conferences 153 (2017): 02002. http://dx.doi.org/10.1051/epjconf/201715302002.

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Maghrabi, Huda Ahmed, Arun Vijayan, Farzad Mohaddes, Pradip Deb, and Lijing Wang. "Evaluation of X-ray radiation shielding performance of barium sulphate-coated fabrics." Fibers and Polymers 17, no. 12 (December 2016): 2047–54. http://dx.doi.org/10.1007/s12221-016-5850-z.

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Kang, Ju Hee, Song Hee Oh, Jung-Il Oh, Seong-Hun Kim, Yong-Suk Choi, and Eui-Hwan Hwang. "Protection evaluation of non-lead radiation-shielding fabric: preliminary exposure-dose study." Oral Radiology 35, no. 3 (June 25, 2018): 224–29. http://dx.doi.org/10.1007/s11282-018-0338-8.

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Xu, Yan, He Xu, Yu Kun Luan, X. Z. Gao, and Kai Xue. "Radiation Characteristics of Heat Sink in Propulsive Wheel of Mobile Robots." Applied Mechanics and Materials 494-495 (February 2014): 1294–97. http://dx.doi.org/10.4028/www.scientific.net/amm.494-495.1294.

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Electromagnetic interference easily appears in the propulsive wheel - a key component of the mobile robots, because internal space of propulsive wheel is very small, there are numerous electronic devices, and signal communication is complex. So electromagnetic shielding is very important for the propulsive wheel. In this paper, a wheel model and an equivalent source model of electromagnetic interference of the wheel were developed based on considerations of the internal electromagnetic properties. At the same time, a secondary source of electromagnetic interference is formed by heat sink. Hence, shielding effectiveness is taken as one of the evaluation criteria for the Electro-Magnetic Compatibility (EMC) problem, and the Genetic Algorithm (GA) in the software Ansoft HFSS platform was used to optimize the first resonance frequency of heat sink.

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Pušić, Tanja, Bosiljka Šaravanja, and Krešimir Malarić. "Electromagnetic Shielding Properties of Knitted Fabric Made from Polyamide Threads Coated with Silver." Materials 14, no. 5 (March 8, 2021): 1281. http://dx.doi.org/10.3390/ma14051281.

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This paper investigates a textile material of low surface mass for its protection against electromagnetic radiation (EMR), which is suitable for composite structures of garments, and for technical and interior applications. The shielding effectiveness against EMR of fabric knitted from polyamide threads coated with silver, measured in the frequency range of 0.9 GHz to 2.4 GHz, indicated a high degree of protection. The key contribution of the paper is the evaluation of the stability of the shielding properties against EM radiation after applying apolar and polar solvents, in synergy with the cyclic process parameters of wet and dry cleaning. The results of the study confirmed the decline in the shielding effectiveness after successive cycles of material treatment with dry and wet cleaning. The effect of wet cleaning in relation to dry cleaning is more apparent, which is due to the damage of the silver coating on the polyamide threads in the knitted fabric.

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Almurayshid, Mansour, Yousif Alssalim, Farouk Aksouh, Rashed Almsalam, Meshari ALQahtani, M. I. Sayyed, and Fahad Almasoud. "Development of New Lead-Free Composite Materials as Potential Radiation Shields." Materials 14, no. 17 (August 30, 2021): 4957. http://dx.doi.org/10.3390/ma14174957.

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Utilizing a polymer-based radiation shield offers lightweight, low cost, non-toxic compared to lead and solution for eliminating generated secondary neutrons. Incorporating silicon (i.e., one of the most abundant elements) in new applications, such as shielding, would have an impact on the economy and industry. In this study, seven potential shielding materials, composed of silicon, silicon carbide, and boron carbide embedded ethylene vinyl acetate (EVA) copolymers, are proposed. The shielding performance of these composite materials, including the attenuation coefficients (µ), the mass attenuation coefficients (µm), the half value layer (HVL), the mean free path (MFP), and the radiation protection efficiency (RPE) were examined using photon beams. Measured µm were verified against the calculated values. The averaged agreement was within ±7.4% between the experimental measurements and the theoretical calculation results. The HVL and MFP measured values for the polymer composites were lower than that for the pure EVA polymer, indicating the fillers in the polymers enhanced the shielding performance. The EVA + SiC (30%) and EVA + Si (15%) + B4C (15%) composites required the lowest thickness to stop 50% of the incident photons. The evaluation of experimental results of the RPE revealed that the polymer composites containing SiC (30%), Si (15%) + B4C (15%), or SiC (15%) + B4C (15%) succeeded in blocking 90–91% of X-rays at nearly 80 keV. However, a thicker shield of the proposed composite materials or combined layers with other high-Z materials could be used for higher energies.

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Nuñez-Briones, A. G., R. Benavides, E. Mendoza-Mendoza, M. E. Martínez-Pardo, H. Carrasco-Abrego, C. Kotzian, F. R. Saucedo-Zendejo, and L. A. García-Cerda. "Preparation of PVC/Bi2O3 composites and their evaluation as low energy X-Ray radiation shielding." Radiation Physics and Chemistry 179 (February 2021): 109198. http://dx.doi.org/10.1016/j.radphyschem.2020.109198.

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Endo, Mime, Yoshihiro Haga, Masahiro Sota, Akiko Tanaka, Kazuki Otomo, Yuuki Murabayashi, Mitsuya Abe, et al. "Evaluation of novel X-ray protective eyewear in reducing the eye dose to interventional radiology physicians." Journal of Radiation Research 62, no. 3 (April 12, 2021): 414–19. http://dx.doi.org/10.1093/jrr/rrab014.

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Abstract The new recommendation of the International Commission on Radiological Protection for occupational eye dose is an equivalent dose limit to the eye of 20 mSv year–1, averaged over a 5-year period. This recommendation is a drastic reduction from the previous limit of 150 mSv year–1. Hence, it is important to protect physicians’ eyes from X-ray radiation. Particularly in interventional radiology (IVR) procedures, many physicians use protective lead (Pb) glasses to reduce their occupational exposure. This study assessed the shielding effects of novel 0.07 mm Pb glasses. The novel glasses (XR-700) have Pb–acrylic lens molded in three dimensions. We studied the novel type of 0.07 mm Pb glasses over a period of seven consecutive months. The eye dose occupational radiation exposure of seven IVR physicians was evaluated during various procedures. All IVR physicians wore eye dosimeters (DOSIRIS™) close to the left side of the left eye. To calculate the shielding effects of the glasses, this same type of eye dosimeter was worn both inside and outside of the Pb lenses. The average shielding effect of the novel glasses across the seven physicians was 61.4%. Our results suggest an improved shielding effect for IVR physicians that use these glasses. No physician complained that the new glasses were uncomfortable; therefore comfort is not a problem. The lightweight glasses were acceptable to IVR physicians, who often must perform long procedures. Thus, the novel glasses are comfortable and reasonably protective. Based on the results of this study, we recommend that IVR physicians use these novel 0.07 mm Pb glasses to reduce their exposure.

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Chen, An Pang, Po Wen Hwang, Ching Wen Lin, Ting An Lin, Ya Yuan Chuang, and Jia Horng Lin. "Manufacturing Technique and Properties Evaluation of Ni-Coated Copper Composite Fabrics." Applied Mechanics and Materials 365-366 (August 2013): 1173–76. http://dx.doi.org/10.4028/www.scientific.net/amm.365-366.1173.

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The existence of the electromagnetic radiation may lead to diseases, which also includes cancer and cause the repellence of electrical compatibility. The textiles which have electromagnetic shielding effectiveness become more important in modern life. In the research, the PET/ Ni-coated Copper composite yarn were made by the wrapping machine, which the core yarn is Ni-coated Copper wire and the wrapped yarn is PET filament. After that, the composite yarn is fabricated by the automatic sampling loom into woven fabrics and had the tests of mechanical properties and electromagnetic shielding effectiveness. The test results revealed that the EMSE of the PET/Ni-Cu complex woven fabrics is 32.28dB, which the test frequency is 900 MHz, laminated layer number is 3 and the laminated angles are 0°/45°/90°, respectively.

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Singh, Vijay, V. P. Singh, N. Singh, Hoonil Jeong, and V. Natarajan. "Ultraviolet B radiation from Gd3+ doped Sr3P4O13: Photoluminescence, electron paramagnetic resonance and evaluation of shielding parameters." Radiation Physics and Chemistry 174 (September 2020): 108956. http://dx.doi.org/10.1016/j.radphyschem.2020.108956.

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Robatjazi, Mostafa, Hamid Reza Baghani, Seied Rabi Mahdavic, and Giuseppe Felici. "Evaluation of dosimetric properties of shielding disk used in intraoperative electron radiotherapy: A Monte Carlo study." Applied Radiation and Isotopes 139 (September 2018): 107–13. http://dx.doi.org/10.1016/j.apradiso.2018.04.037.

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Koťátková, Jaroslava, Jan Zatloukal, Pavel Reiterman, Jan Patera, Zbyněk Hlaváč, and Petr Brabec. "The Effect of Elevated Temperatures and Nuclear Radiation on the Properties of Biological Shielding Concrete." Key Engineering Materials 677 (January 2016): 8–16. http://dx.doi.org/10.4028/www.scientific.net/kem.677.8.

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The paper reviews the so far known information about the properties of biological shielding concrete used in the containment vessel of nuclear power plants (NPP) and its behaviour when exposed to radiation. The damage of concrete caused by neutron and gamma radiation as well as by the accompanying generation of heat is described. However, there is not enough data for the proper evaluation of the negative impacts and further research is needed.

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