Relevant bibliographies by topics / Gamma radiation shielding

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers

Academic literature on the topic 'Gamma radiation shielding'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 February 2022

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Journal articles on the topic "Gamma radiation shielding"

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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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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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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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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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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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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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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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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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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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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Dissertations / Theses on the topic "Gamma radiation shielding"

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Konček, Róbert. "Simulace stínění ionizujícího záření programem MCNP." Master's thesis, Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií, 2015. http://www.nusl.cz/ntk/nusl-221214.

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Radiation is defined as ionizing if it has enough energy to remove electrons from atoms or molecules when it passes through or collides with matter. This ability implies potentially detrimental effects on living tissue. Ionizing radiation shielding is therefore a discipline of great practical importance. The thesis builds upon the author's previous work on the topic and widens the scope of discussion with theoretical and practical issues of advanced shielding calculations. The theoretical part of the thesis describes several approaches to calculating fluence or absorbed dose at an arbitrary po
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ALBUQUERQUE, SERGIO M. de. "Estudo para o desenvolvimento e caracterização de concretos de mass específica elevada para proteção às radiações gama e X." reponame:Repositório Institucional do IPEN, 2014. http://repositorio.ipen.br:8080/xmlui/handle/123456789/11808.

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Submitted by Claudinei Pracidelli (cpracide@ipen.br) on 2014-11-10T12:20:07Z No. of bitstreams: 0<br>Made available in DSpace on 2014-11-10T12:20:07Z (GMT). No. of bitstreams: 0<br>Tese (Doutorado em Tecnologia Nuclear)<br>IPEN/T<br>Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Flaspoehler, Timothy Michael. "FW-CADIS variance reduction in MAVRIC shielding analysis of the VHTR." Thesis, Georgia Institute of Technology, 2012. http://hdl.handle.net/1853/45743.

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In the following work, the MAVRIC sequence of the Scale6.1 code package was tested for its efficacy in calculating a wide range of shielding parameters with respect to HTGRs. One of the NGNP designs that has gained large support internationally is the VHTR. The development of the Scale6.1 code package at ORNL has been primarily directed towards supporting the current United States' reactor fleet of LWR technology. Since plans have been made to build a prototype VHTR, it is important to verify that the MAVRIC sequence can adequately meet the simulation needs of a different reactor technology
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Tadadjeu, Sokeng Ifriky. "Sub-10 MeV proton irradiation effects on a coating obtained from the pulsed laser ablation of W2B5/B4C for space applications." Thesis, Cape Peninsula University of Technology, 2015. http://hdl.handle.net/20.500.11838/2181.

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Thesis submitted in partial fulfilment of the requirements for the degree Doctor of Technology: Electrical, Electronic and Computer Engineering in the Faculty of Engineering at the Cape Peninsula University of Technology<br>This research investigates the effects of sub-10 MeV protons on coatings obtained from the pulsed laser ablation of W2B5/B4C. This is in an attempt to extend the bullet proof applications of W2B5/B4C to space radiation shielding applications, offering low cost and low mass protection against radiation including X-rays, neutrons, gamma rays and protons in low Earth orbit.
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Nygren, Nelly. "Optimization of the Gamma Knife Treatment Room Design." Thesis, KTH, Fysik, 2021. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-300904.

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Radiation shielding is a central part of the design of treatment rooms for radiation therapy systems. The dose levels that medical staff and members of the public can be exposed to outside the treatment rooms are regulated by authorities and influence the required wall thicknesses and possible locations for the systems. Several standard methods exist for performing shielding calculations, but they are not well adapted to the stereotactic radiosurgery system Leksell Gamma Knife because of its self-shielding properties. The built-in shielding makes the leakage radiation anisotropic and generally
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Albuquerque, Sérgio Medeiros de. "Estudo para o desenvolvimento e caracterização de concretos de massa específica elevada para proteção às radiações gama e X." Universidade de São Paulo, 2014. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-06102014-090452/.

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Este trabalho de tese de doutorado visou identificar as matérias primas naturais produzidas no Brasil e possíveis de serem utilizadas na produção de concretos de elevada massa específica. Desenvolver uma metodologia para a caracterização, preparo, moldagem, ensaios para determinação do coeficiente de atenuação linear experimental, calculo do coeficiente de atenuação linear teórico, e determinação do Z efetivo, culminando com a confecção de um banco de dados embrionário para os concretos de elevada massa específica preparados com matérias primas nacionais. Para tanto foram identificadas onze ma
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Hubert, Alexis. "Spectroscopic Study of Radiation around the Leksell Gamma Knife for Room Shielding Applications." Thesis, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-202108.

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Any center planning to install a Gamma Knife radiosurgery unit has to provide for an efficient shielding of the treatment room, to protect the patient, the staff and the public, against undesired radiation. The shielding barrier design is controlled by national and international recommendations; the reference documents for gamma ray radiotherapy facilities are the National Council on Radiation Protection and Measurements (NCRP) reports 49 and 151. However, some facts highlighted in this thesis point out that NCRP methods are ill-adapted to the Gamma Knife. Spectroscopic measurements were perfo
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Thompson, Kyle Richard. "Modeling of gamma rays streaming through straight rectangular ducts." 1985. http://hdl.handle.net/2097/27559.

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Hinderer, James Howard. "Radioisotopic Impurities in Promethium-147 Produced at the ORNL High Flux Isotope Reactor." 2010. http://trace.tennessee.edu/utk_gradthes/717.

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There is an intense interest in the availability of radioactive isotopes that could be developed into nuclear batteries. Promethium-147 is one of the isotopes of interest for use in nuclear batteries as well as in other compact low power applications. Pm-147 is a pure beta (β-) emitter with a half-life of 2.62 years. For this research, Pm-147 was produced from enriched Nd-146 via the neutron capture method in the Hydraulic Tube facility of HFIR at the Oak Ridge National Laboratory. Radioisotopic impurities produced via the neutron capture method have significant effects on its potential fi
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Christian, Jose L. 1963. "Use of raw Martian and Lunar soils for surface-based reactor shielding." Thesis, 2010. http://hdl.handle.net/2152/26496.

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For several decades, the idea of flying and landing a less-than-man-rated nuclear reactor for planetary surface applications has been considered. This approach promises significant mass savings and therefore reduction in launch cost. To compensate for the lack of shielding, it has been suggested the use of in-situ materials for providing radiation protection. This would take the form of either raw dirt walls or processed soil materials into blocks or tile elements. As a first step in determining the suitability of this approach, it is necessary to understand the neutron activation characte
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Books on the topic "Gamma radiation shielding"

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Practical radiation safety manual. International Atomic Energy Agency, 1992.

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R, Gaier James, and United States. National Aeronautics and Space Administration., eds. Effect of intercalation in graphite epoxy composites on the shielding of high energy radiation. National Aeronautics and Space Administration, 1997.

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R, Gaier James, and Ames Research Center, eds. Effect of intercalation in graphite epoxy composites on the shielding of high energy radiation. National Aeronautics and Space Administration, 1997.

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J, Frasca A., and United States. National Aeronautics and Space Administration., eds. Neutron and gamma irradiation effects on power semiconductor switches. NASA, 1990.

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Peet, Deborah J., Patrick Horton, Colin J. Martin, and David G. Sutton. Radiotherapy: external beam radiotherapy. Oxford University Press, 2015. http://dx.doi.org/10.1093/med/9780199655212.003.0019.

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Design principles for radiotherapy facilities using X-ray, γ‎-ray, and electron beams are described, especially the requirements for primary and secondary shielding and maze and door entrances. These features are illustrated with reference to the shielded rooms (bunkers) required for linear accelerators, and example calculations are included for shielding and maze design to achieve required dose constraints. The impact of new clinical practices with intensity modulated radiation fields and flattening filter-free operation is also considered. Engineering controls and features for safe operation
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Structural Shielding Design And Evaluation for Megavoltage X-and Gamma-ray Radiotherapy Facilities: Recommendations of the National Council on Radiation ... And Measurements (Ncrp Report Series). National Council of Teachers of English, 2005.

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Book chapters on the topic "Gamma radiation shielding"

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Wolff, Dietmar, Kerstin von der Ehe, Matthias Jaunich, Martin Böhning, and Harald Goering. "(U)HMWPE as Neutron Radiation Shielding Materials: Impact of Gamma Radiation on Structure and Properties." In Effects of Radiation on Nuclear Materials: 25th Volume. ASTM International, 2012. http://dx.doi.org/10.1520/stp103980.

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Almeida, Airton T., M. A. Pereira dos Santos, M. S. Nogueira Tavares, and J. A. Filho. "Characterization of Barite and Crystal Glass as Attenuators in x-Ray and Gamma Radiation Shielding." In IFMBE Proceedings. Springer Berlin Heidelberg, 2009. http://dx.doi.org/10.1007/978-3-642-03902-7_84.

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de Oliveira e Silva, José Anisio. "Effective Shielding of Gamma Radiation in Field Conditions." In Non-destructive Testing '92. Elsevier, 1992. http://dx.doi.org/10.1016/b978-0-444-89791-6.50140-2.

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"sorbed dose must be measured by placing dose meters into the carriers, as described in Section V. If all of the gamma radiation coming from the 60Co source were absorbed by the irradiated goods, the radiation facility would have % irradiation efficiency. This is of course impossible because some of the radiation will be absorbed by the concrete shielding, by the carrier metal, and by the water below the source rack. Well-designed gamma facilities have an efficiency of about 30%. Designs differ­ ent from that shown in Figure 3 may use tote boxes on a conveyor belt instead of carriers hanging from a monorail, or the carriers may move around the source in a double loop instead of a single loop. Storage of the radioactive source in air in a concrete-shielded or lead-shielded cask instead of the water pool is also possible but is not often practiced. The outside appearance of a gamma irradiation facility is not much different from that of any other small or medium size industrial plant. A view of the first irradiation plant in the United States designed exclusively for the processing of foods (1) is shown in Figure 4. In principle, a 137Cs irradiator operates exactly like a 60Co irradiator. Some­ what less concrete shielding (1.2 m) is needed because the 0.66 MeV gamma rays of ,37Cs are less penetrating than the 1.33 MeV of Co. The longer half-life of." In Safety of Irradiated Foods. CRC Press, 1995. http://dx.doi.org/10.1201/9781482273168-25.

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Conference papers on the topic "Gamma radiation shielding"

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Serikov, Arkady. "Shielding Analyses for Gamma Spectrometer GAMMACELL in Experiments on Neutron Generator." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49196.

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The paper is devoted to computational analysis of shielding properties of spectrometer GAMMACELL irradiated by neutrons from 14.1 MeV Neutron Generator (NG). The shielding is required to protect the BaF2 crystals of the gamma spectrometer GAMMACELL from background thermal neutrons, scattered from the walls and equipment in experimental room. GAMMACELL is a scintillation spectrometer of full gamma particles absorption. It consists of 9 BaF2 crystals; each of them has 40×40×100 mm3 dimensions and is viewed by photomultiplier tube. Neutrons also cause flashes in BaF2 crystals and give spurious pu
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Tian, Yingnan, Lin Long, Puzhong Zhang, et al. "Radiation Shielding Analysis of Radioactive Material Product Container." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67673.

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For nuclear fuel reprocessing plants, some materials with high activity have been collected in the product container in the process of spent fuel reprocessing. In order to ensure the staff’s occupational radiation safety, an analysis of product container radiation shielding and source terms is crucial to determine the total activity limit and the activity limit range of different rays while reprocessing radioactive materials in the product container, so as to determine the working time limitation. A basic calculation result shows that generally alpha particles are not taken into consideration
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Bin Sazali, Muhammad Arif, Nahrul Khair Alang Md Rashid, and Khaidzir Hamzah. "Ant Colony Optimization of Multilayer Shielding for Mixed Neutron and Gamma Radiations: A Preliminary Study." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67765.

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Mixed neutron and gamma radiations require different shielding materials as their interaction with materials is different. Composites were developed in order to combine the shielding capabilities of different materials. However, their homogeneity is difficult to be assured which can lead to pinholes where radiation can penetrate. To avoid this problem, several materials arranged in layers can be used to shield against mixed radiations. Since the multilayer shielding can be made from any material in many configurations, the ant colony optimization (ACO) is a promising method because it deals wi
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Kaur, Pardeep, Dalip Singh, Tejbir Singh, and Preet Kaur. "Gamma radiation shielding characteristics for some rare earth doped lead borate glasses." In ADVANCED MATERIALS AND RADIATION PHYSICS (AMRP-2020): 5th National e-Conference on Advanced Materials and Radiation Physics. AIP Publishing, 2021. http://dx.doi.org/10.1063/5.0053029.

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Ashayer, Sahar, Mansur Asgari, and Hossein Afarideh. "Optimizing Gamma-Ray Shielding Material by Using Genetic Algorithm and MCNP Code." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29018.

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Radiation shielding material investigations is an important subject which relates to human safety, for those engaging in medical radiation, radiology, and facilities related with nuclear radiation, manned spacecraft and so on. Therefore necessity of finding effective shielding materials which have low weight, and cost, and have stability against radiation, with high temperature resistant, and no biological damage,… is obvious. On the other hand, because of the multi-variability of the problem, it is experimentally difficult to determine the optimum values of the concerned variables. For this r
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Singh, Sukhpal. "Molar volume, elastic and gamma radiation shielding parameters of Bismuth-Niobium-Aluminosilicate glasses." In ADVANCED MATERIALS AND RADIATION PHYSICS (AMRP-2020): 5th National e-Conference on Advanced Materials and Radiation Physics. AIP Publishing, 2021. http://dx.doi.org/10.1063/5.0052328.

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Pahladsingh, Remond R. "Possibility of Using Gamma Radiation From HTR Reactors for Processing of Food and Medical Products." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49316.

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During the fission process in most of the presently operating nuclear reactors nuclear energy is converted into thermal energy and transferred to common steamcycles for powergeneration. As part of the fission process also α-, β- and neutrons particles are released from the nucleus; the release of gamma-rays is also a part of the fission process. In present nuclear reactors α-, β-, neutrons particles and particularly Gamma-rays are not gainfully used as a result of the reactor design and of the containment. These plants are built as required by regulations and international standards for safety
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Kaur, Parminder, K. J. Singh, and Sonika Thakur. "Evaluation of the gamma radiation shielding parameters of bismuth modified quaternary glass system." In 2ND INTERNATIONAL CONFERENCE ON CONDENSED MATTER AND APPLIED PHYSICS (ICC 2017). Author(s), 2018. http://dx.doi.org/10.1063/1.5032878.

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Tawara, Yuzuru, Shinji Hara, Kazuo Koga, and Kenji Tsuji. "Application of Cloud Chambers for Heuristic Comprehension of Radiation." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16909.

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In the nuclear-related public relation center, a variety of displays such as models of nuclear facility, panel presentations to explain radiation properties, radiation detectors are used for the visitors to help the understanding of nuclear power and radiation. The PR center demonstrates various aspect of the radiation such as the presence of natural background radiations around us in the daily life, shielding effect for the different kind of radiations. Cloud Chambers are often used to demonstrate the presence of natural background radiation, showing tracks caused by the ionizing effect. The
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Sidhu, Baltej Singh, A. S. Dhaliwal, and K. S. Kahlon. "Investigation of gamma ray and fast neutron shielding ability of some waste glasses for nuclear waste storage facilities." In ADVANCED MATERIALS AND RADIATION PHYSICS (AMRP-2020): 5th National e-Conference on Advanced Materials and Radiation Physics. AIP Publishing, 2021. http://dx.doi.org/10.1063/5.0052727.

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