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Radiation Shielding Materials (Volume II)

A special issue of Materials (ISSN 1996-1944). This special issue belongs to the section "Advanced Composites".

Deadline for manuscript submissions: closed (10 June 2023) | Viewed by 3535

Special Issue Editors


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Guest Editor
1. Department of physics, Faculty of Science, Isra University, Amman, Jordan
2. Department of Nuclear Medicine Research, Institute for Research and Medical Consultations (IRMC), Imam Abdulrahman Bin Faisal University (IAU), P.O. Box 1982, Dammam 31441, Saudi Arabia
Interests: ionizing radiation; radiation shielding materials; heavy metal oxide glasses; Monte Carlo simulation; nanomaterials for radiation protection; ceramics for radiation shielding applications; radiation shielding for medical applications
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Guest Editor
1. Laboratory of Single Crystal Growth, South Ural State University, 454080 Chelyabinsk, Russia
2. Scientific-Practical Materials Research Centre of the National Academy of Sciences of Belarus, 220072 Minsk, Belarus
Interests: electrochemical analysis; material characterization; nanomaterials; electrodeposition; materials; nanomaterials synthesis; self-assembled monolayers; nanostructured materials
Special Issues, Collections and Topics in MDPI journals

Special Issue Information

Dear Colleagues,

With the increased use of radiation across vast fields of work, it is necessary to also develop radiation shields that can adequately protect the bodies of workers and patients that come into contact with high-energy photons. Radiation shields, or materials that are used to absorb radiation, are necessary to properly attenuate ionizing radiation, which is defined as radiation that has sufficient energy to detach electrons from atoms. Long-term human exposure to ionizing radiation can cause permanent tissue damage, acute radiation syndrome, cancer, and death in extreme cases. Thus, to prevent these effects, workers and patients must be provided with efficient radiation shields that will lower the levels of radiation to safe enough levels.

When deciding on a material to use to attenuate radiation, several specific aspects of application must be considered, such as the energies of incoming photons, the environmental conditions of the radiation source (indoors or outdoors), whether transparency is necessary, etc. Because of these varying uses, a shield that may be ideal for one specific situation may not be an effective shield in another. Some examples of commonly used radiation shielding materials include concrete, alloys, pure lead, and glasses. All these materials offer their own unique pros and cons but are receiving attention by various researchers in the radiation shielding community to attempt to discover the ideal shielding material for each application.

The Special Issue on “Radiation Shielding Materials (Volume II)” will focus on novel materials used for radiation protection applications in different fields, such as medicine, science, nuclear industry, electronics, and aerospace.

Dr. M.I. Sayyed
Dr. Daria Tishkevich
Guest Editors

Manuscript Submission Information

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Please visit the Instructions for Authors page before submitting a manuscript. The Article Processing Charge (APC) for publication in this open access journal is 2600 CHF (Swiss Francs). Submitted papers should be well formatted and use good English. Authors may use MDPI's English editing service prior to publication or during author revisions.

Keywords

  • ionizing radiation
  • radiation shielding
  • electromagnetic shielding
  • computer simulation
  • glasses as shielding materials
  • ceramics as shielding materials
  • films and coatings as shielding materials
  • attenuation factors
  • radioisotopes
  • morphological, structural, mechanical, optical, and radiation shielding properties

Related Special Issue

Published Papers (2 papers)

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Research

15 pages, 2890 KiB  
Article
Assessment of Five Concrete Types as Candidate Shielding Materials for a Compact Radiation Source Based on the IECF
by Rawheya Ahmed, Galal Saad Hassan, Thomas Scott and Mahmoud Bakr
Materials 2023, 16(7), 2845; https://doi.org/10.3390/ma16072845 - 03 Apr 2023
Cited by 3 | Viewed by 1530
Abstract
A radiation source based on the inertial electrostatic confinement fusion (IECF) system is being developed for multidisciplinary research applications. The radiation outputs from the IECF system are 2.45 MeV fast neutrons and the associated co-generated X-rays with an energy less than 3 MeV. [...] Read more.
A radiation source based on the inertial electrostatic confinement fusion (IECF) system is being developed for multidisciplinary research applications. The radiation outputs from the IECF system are 2.45 MeV fast neutrons and the associated co-generated X-rays with an energy less than 3 MeV. A radiation shielding study has been performed on five types of concrete to define the most efficient material for the shielding design of the system. The proposed materials were ilmenite-magnetite concrete (IMC), ordinary concrete-1 (OC-1), barite-containing concrete (BC), ordinary concrete-2 (OC-2), and serpentine-containing concrete (SC). A numerical model was applied to determine the effective removal cross-section coefficients (∑Rt) for the fast neutrons and the total mass attenuation coefficients (µm), the half-value layer (HVL), the mean free path (MFP), the effective atomic number (Zeff), and effective electron density (Neff) for photons inside the materials. The model considered the radiation source energy and the material properties of the concrete types. The results revealed that the serpentine-containing concrete exhibited the highest ∑Rt with 12 cm of concrete thickness needed to attenuate an incident neutron flux to 1/100 of its initial value. In addition, the BC shows the highest µm with a 38 cm concrete thickness needed to attenuate the 3 MeV energy X-ray flux to 1/100 of its initial value. This study suggests that a 40 cm thickness of SC or BC adequately shields the radiation generated from an IECF system with a maximum particle production rate of up to 1 × 107 n/s. Full article
(This article belongs to the Special Issue Radiation Shielding Materials (Volume II))
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14 pages, 3771 KiB  
Article
Developed a New Radiation Shielding Absorber Composed of Waste Marble, Polyester, PbCO3, and CdO to Reduce Waste Marble Considering Environmental Safety
by M. I. Sayyed, Mansour Almurayshid, Fahad I. Almasoud, Amjad R. Alyahyawi, Sabina Yasmin and Mohamed Elsafi
Materials 2022, 15(23), 8371; https://doi.org/10.3390/ma15238371 - 24 Nov 2022
Cited by 13 | Viewed by 1464
Abstract
The usage of radiation is mandatory for modern life; in the same manner, controlling the outflow of harmful radiation is vital and could be achieved via employing a shielding material to eliminate any potential nuclear and radiation accidents and incidents. Considering this point, [...] Read more.
The usage of radiation is mandatory for modern life; in the same manner, controlling the outflow of harmful radiation is vital and could be achieved via employing a shielding material to eliminate any potential nuclear and radiation accidents and incidents. Considering this point, this study aims to manufacture composite samples based on waste marble as novel radiation shields. The physical and radiation shielding ability of the prepared shields were determined and analyzed. For this purpose, a high-purity germanium (HPGe) detector was used to detect the incoming photons emitted from three point sources (Am-241, Cs-137, and Co-60). The radiation attenuation factors for the new marble-based composites were measured for some energies, ranging from 0.06 to 1.333 MeV. We examined the effect of increasing the PbCO3 and CdO contents on the physical properties and radiation attenuation factors of the newly developed radiation shielding absorber. We found that the density of the samples increases from 1.784 to 1.796 g/cm3 when the CdO changes from 0 to 12.5 wt%. The linear attenuation coefficient (LAC) for all marble compositions has the maximum value at 0.06 MeV, while the LAC decreases with increasing energy. The highest LAC was found for Marb-3, with a composition of waste marble (50 wt%), polyester (25 wt%), PbCO3 (17.5 wt%), and CdO (7.5 wt%). We studied the impact of the addition of CdO on the expense of PbCO3 and we found that the half value layer (HVL) decreases with increasing the CdO content. Hence, when there is no space problem, the newly developed radiation shielding absorber can be used to maintain the cost effectiveness and environmentally friendliness of products. Full article
(This article belongs to the Special Issue Radiation Shielding Materials (Volume II))
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