Concrete For Radiation Shielding Research Articles

Valorization of steel slag into sustainable high-performance radiation shielding concrete

The disposal of steel slag (SS) has become a serious ecological problem due to the waste of massive land resources. This study reveals the huge potential of recycling SS as heavy aggregates to develop radiation shielding concrete (RSC). The physical characteristics, radiation attenuation capabilities, microstructure, and environmental and ecological impacts of SS-based RSC are comprehensively evaluated and compared with those of normal concrete and the commonly used heavy concrete. The test results indicate that SS-based RSC is prospective to substitute the commonly used heavy concrete, emerging as a sustainable and efficient material for radiation shielding in nuclear energy engineering. Specifically, due to the reaction of cementitious active substances in the surface of SS, the developed SS-based RSC exhibits a fantastic interfacial transition zone (ITZ), and a compact pore structure, thereby showing excellent mechanical properties. The maximum compressive strength of developed SS-based RSC reaches 47.4 MPa. In terms of gamma ray attenuation property, due to the introduction of heavy nuclei and the increase in density, the gamma ray attenuation capacity of developed SS-based RSC is 17.2 % higher than that of normal concrete. The neutron attenuation property is also slightly enhanced due to the refinement effect of SS on pore structure of RSC. Life cycle assessment and unit cost evaluation results demonstrate that compared with barite based-RSC, SS-based RSC can save 97.6 % in cost, 52.0 % in energy consumption, and 70.4 % in carbon emission. The developed SS-based RSC exhibits excellent mechanical properties and radiation attenuation capacities, contributing to the further application of radiation shielding materials. Besides, this approach achieves the high-value recycling of SS, providing new insights for the utilization of high-density solid wastes.

Effect of High Temperatures on Mechanical and Shielding Properties of Lead–Zinc Tailings Concrete for Radiation Protection

Due to the high prices, the popularity of radiation shielding concrete (RSC) has been greatly limited. To solve this, this research reused the lead–zinc tailings (LZT) as a fine aggregate replacement ranging from 0% to 60% for the RSC. The results revealed that the RSC containing 30% LZT presented better workability and achieved 95.84% of the compressive strength and 98.49% of the linear attenuation coefficient of the RSC, and reached the highest splitting tensile strength values, which increased by 4.43%. Meanwhile, after the heat treatments, there were favorable correlations between the relative velocity and relative strength, as well as between the damage index and the relative linear attenuation coefficient, which could accurately reflect the degradation of not only the mechanical but also the shielding properties. Considering the temperature and shielding thickness, the reuse of LZT can bring considerable economic and environmental benefits.

Microstructure and radiation shielding properties of lead-fiber reinforced high-performance concrete

The increasing application of nuclear technology in medical fields has amplified the demand for radiation shielding materials. Traditional large-volume concrete cannot simultaneously exhibit excellent neutron and gamma-ray shielding capabilities while ensuring superior mechanical properties. This study tailored a novel lead fiber-reinforced high-performance concrete (LFRHPC) with lead fibers and magnetite aggregates, focusing on radiation attenuation. The effect of lead fibers on the mechanical performance, microstructure and radiation attenuation characteristics for LFRHPC was comprehensively evaluated. The results indicate a significant improvement in the mechanical performance of LFRHPC compared to traditional radiation shielding concrete (RSC), due to the scientific skeleton design. Additionally, the pore structure in LFRHPC is refined by incorporating lead fibers. Moreover, the interfacial transition zone (ITZ) between the cementitious matrix and magnetite is improved because of the very low water-to-binder ratio. To assess the radiation attenuation ability of LFRHPC, both direct measurements and simulation models were utilized. The data reveals that the porosity of LFRHPC plays a crucial role in its shielding effectiveness against neutron and gamma radiation. Furthermore, the addition of lead fibers considerably boosts its neutron and gamma-ray shielding attenuation capabilities. In summation, LFRHPC combines excellent mechanical properties and radiation shielding capabilities, making it suitable for construction applications in medical settings.

Mechanics, γ-ray shielding properties and acoustic emission characteristics of radiation shielding concrete exposed to elevated temperatures

High temperature can cause serious damage to building structures, so it is important in order to re-evaluate the residual properties of radiation shielding concrete (RSC) exposed to elevated temperatures for ensuring security of medical, industrial and defense building structures. Thus, the deterioration of the mechanical, γ-ray shielding properties and acoustic emission characteristics of barite concrete (BC) and magnetite concrete (MC) exposed to elevated temperatures were studied. Research indicated that the performance of aggregates played a crucial role in the thermal stability, residual physical and mechanical properties of concrete exposed to elevated temperatures. BC was subjected from bursting and even spalling at 300 °C, while its physical and mechanical properties deteriorated drastically. However, MC still had favorable integrity and relatively high residual mechanical properties at 800 °C. The maximum deterioration temperature of BC exposed to elevated temperatures occurred at about 300 °C, while that of MC occurred at 450–600 °C. The degradation of the γ-ray shielding properties of RSC exposed to elevated temperatures was significantly lower than its mechanical properties.

Value-added recycling of cathode ray tube funnel glass into high-performance radiation shielding concrete

This study proposed a novel method for recycling cathode ray tube (CRT) glass as heavy aggregates to prepare radiation shielding concrete (RSC). Microstructure, physical properties, radiation shielding characteristics, as well as economic and environmental benefits of CRT glass-based RSC were evaluated. Compared to conventional RSC, the CRT glass-based RSC showed a 13.8 % higher gamma ray shielding capacity. Although the mechanical properties of CRT glass-based RSC slightly decreased by 25.7 % due to the weak interfacial transition zone, the 28-day compressive strength of CRT glass-based RSC still fulfilled the requirement of criteria (> 30 MPa). Based on the cost-benefit assessment, there was 166.7 $/m3 profit in CRT glass-based RSC. Furthermore, CRT glass-based RSC demonstrated 47.7 % and 37.0 % reduction in fossil fuel depletion and carbon emissions compared with barite-based RSC.

Valorization of hazardous chrysotile by H3BO3 incorporation to produce an innovative eco-friendly radiation shielding concrete: Implications on physico-mechanical, hydration, microstructural, and shielding properties

For the first time, the hazardous chrysotile was valorized as an aggregate in radiation shielding concrete (RSC). This was accomplished through its amalgamation with two different ratios of boric acid (H3BO3) by 1 and 3% of cement mass to produce CR1, and CR2 concrete mixtures, respectively, in comparison with zero H3BO3 in the control concrete (CC). Physico-mechanical, hydration, and microstructural properties of these concrete mixtures were analyzed employing X-ray diffraction (XRD), Fourier transformation infrared spectroscopy (FTIR), X-ray fluorescence (XRF), scanning electron microscopy (SEM), thermogravimetry/its derivative (TG/DTG), and physico-mechanical tests. Additionally, the radiation shielding was evaluated using Pu–Be, and 60Co sources. Computational studies using NXcom, and WinXCom, as theoretical calculation programs accompanied by the MCNP-5 code as a simulation tool, were applied to verify the radiation shielding measurements. The findings showed that the CC has reasonable radiation shielding with acceptable physico-mechanical properties. On the contrary, CR1 and CR2 had deleterious mechanical and microstructural properties, but more enhanced neutron shielding properties compared to their precursor CC. This conclusion was verified by the remarkable compatibility between the computational and experimental outcomes. Ultimately, H3BO3 additions boosted the radiation shielding of chrysotile concrete despite their devastating impact on the mechanical and microstructural properties, emphasizing the eligibility of chrysotile as an aggregate in RSC.

Using serpentine in concrete: A literature review

Concrete is the most important and extensively used building material. It is used for various functions, including shielding materials from radiation sources such as nuclear power plants. Nuclear technology is applied in numerous research institutes, enterprises, and healthcare facilities, in addition to the exposure to radiation from power plants. Concrete has been considered as a potential shielding material by a number of researchers due to its low cost, durability, and strength, as well as the fact that it can be made using readily available materials. Numerous concrete technologists have turned to materials such as Serpentine to make heavy-weight concrete for radiation shielding against different levels of gamma rays and neutron shielding. This review investigates the radiation shielding materials of Serpentine and materials containing Serpentine mineral, such as Green Marble, in the building industry. This review study is divided into two primary areas: serpentine concrete and the use of serpentine aggregates as a radiation shielding material in concrete. Concrete mixtures using Serpentine alone and in combination with other efficient materials like boric acid and other minerals were used to create radiation-shielding concrete (RSC). On the basis of experimental data, the indicator of radiation shielding performance and the unit weight of concrete was found to have a correlation with a high degree of fitting. The objective of this study is to review the use of Serpentine with concrete and to provide direction on the difficulties encountered in the research process so far regarding the use of the mining waste from serpentine rock in concrete.

Deep Insights into the Radiation Shielding Features of Heavy Minerals in Their Native Status: Implications for Their Physical, Mineralogical, Geochemical, and Morphological Properties

Barite and hematite are the most common heavy-weight minerals applied as aggregates in radiation shielding concrete (RSC). Therefore, to limit the cement consumption and reduce the CO2 emissions accompanying its production, the aim of this study is to use Egyptian barite and hematite minerals in their native status and evaluate their attenuation efficiency against fast neutrons and γ-rays. This was implemented through the measurement of their radiation attenuation against fast neutrons and γ-rays in the energy ranges of 0.80–11 and 0.40–8.30 MeV, respectively, employing a Pu-Be source and a stilbene scintillator. Theoretical calculations were prepared using the NXcom program to validate the fast neutron attenuation measurements. Furthermore, the implications of the physical, mineralogical, geochemical, and morphological characteristics of these heavy-weight minerals with respect to their attenuation efficiencies were considered. We found that barite has superior radiation attenuation efficiency for fast neutrons and γ-rays compared to hematite by 9.17 and 51% for fast neutrons and γ-rays, respectively. This was ascribed to the superior physical, mineralogical, geochemical, and morphological properties of the former relative to those of the latter. Furthermore, a satisfactory agreement between the experimental and theoretical results was achieved, with a deviation of 16 and 19.25% for the barite and hematite samples, respectively. Eventually, barite and hematite can be successful candidates for their use as sustainable alternatives to common RSC.

Radiation Attenuation Assessment of Serpentinite Rocks from a Geological Perspective.

Serpentinites are metamorphic rocks that are widely applied as aggregates in the production of radiation-shielding concrete. Different varieties of massive serpentinite mountains located in Egypt exist without real investment. Hence, this study aims to evaluate the radiation shielding efficacy of three varieties of serpentinite rocks from different geological perspectives: mineralogical, geochemical, and morphological characteristics. X-ray diffraction, transmitted-light microscopy, and thermal analysis were required to characterize their mineralogical composition, while X-ray fluorescence was necessary to investigate their geochemical features. Moreover, scanning electron microscopy was used to detect their morphological characteristics. On the other hand, the PuBe source and stilbene detector were employed for the experimental determination of fast neutrons and γ-ray attenuations, which were conducted at energy ranges of 0.8-11 and 0.4-8.3 MeV, respectively. Based on the mineralogical, geochemical, and morphological characteristics of these rocks, the radiation attenuation capacity of lizardite > antigorite > chrysotile. However, these serpentinites can be applied as a natural alternative to some radiation-shielding concrete in radiotherapy centers and other counterpart facilities.

Green Conversion of the Hazardous Cathode Ray Tube and Red Mud into Radiation Shielding Concrete.

The present investigation was aimed at the utilization of alternate materials, emphasizing hazardous industrial products (red mud and cathode ray tubes), as constituents of radiation shielding concrete. The usage of these hazardous industrial products improves the sustainability and performance of the radiation shielding concrete. Five concrete blocks were cast and their density, compressive strength, gamma shielding factors, radiation absorption ratio, and transmission factor were explored. For this purpose, gamma-ray shielding measurements were done with the help of an HPGe detector. Mix-1, with zero contents of red mud and CRTs, had the lowest LAC. The LAC results demonstrated that the shielding performance of the current concretes would be better with the increase in red mud and cathode ray tube glass. The Transmission factor (TF) for the prepared concretes with a thickness of 2 cm varied between 11.9–26.1% at 0.06 MeV, while it varied between 4–13% for a thickness of 3 cm. The TF results showed that the composites with a thickness of 2, 3, or 5 cm are good shields against lower energy radiation. The radiation absorption ratio (RAR) for the prepared concretes is high at low energy, suggesting that these new composites can absorb most of the low-energy photons. The RAR results emphasize that the increase in CRTs in the new composites enhanced the radiation shielding features, and when the CRT glass is at a maximum, more attenuation was achieved.

Recent Trends in Advanced Radiation Shielding Concrete for Construction of Facilities: Materials and Properties

Nuclear energy offers a wide range of applications, which include power generation, X-ray imaging, and non-destructive tests, in many economic sectors. However, such applications come with the risk of harmful radiation, thereby requiring shielding to prevent harmful effects on the surrounding environment and users. Concrete has long been used as part of structures in nuclear power plants, X-ray imaging rooms, and radioactive storage. The direction of recent research is headed toward concrete’s ability in attenuating harmful energy radiated from nuclear sources through various alterations to its composition. Radiation shielding concrete (RSC) is a composite-based concrete that was developed in the last few years with heavy natural aggregates such as magnetite or barites. RSC is deemed a superior alternative to many types of traditional normal concrete in terms of shielding against the harmful radiation, and being economical and moldable. Given the merits of RSCs, this article presents a comprehensive review on the subject, considering the classifications, alternative materials, design additives, and type of heavy aggregates used. This literature review also provides critical reviews on RSC performance in terms of radiation shielding characteristics, mechanical strength, and durability. In addition, this work extensively reviews the trends of development research toward a broad understanding of the application possibilities of RSC as an advanced concrete product for producing a robust and green concrete composite for the construction of radiation shielding facilities as a better solution for protection from sources of radiation. Furthermore, this critical review provides a view of the progress made on RSCs and proposes avenues for future research on this hotspot research topic.

Use of barite concrete for radiation shielding against gamma-rays and neutrons

Demand to use nuclear technology in medicine and research in Thailand is increasing. Therefore, the objective of the present study was to analyze the performance of concrete containing local minerals, barite and cut steel bars in protecting against gamma-ray and fast-neutron radiation. Using barite as fine and coarse aggregates in concrete increases the radiation shielding capability, as well as the strength and density of specimens. Using cut steel bars as an additive material significantly increases the attenuation coefficients of gamma-rays and neutrons.

Green Conversion of the Hazardous Cathode Ray Tube and Red Mud into Radiation Shielding Concrete

Green Conversion of the Hazardous Cathode Ray Tube and Red Mud into Radiation Shielding Concrete

Assessment of Long Lived Isotopes in Alkali-Silica Resistant Concrete Designed for Nuclear Installations.

The design of concrete for radiation shielding structures is principally based on the selection of materials of adequate elemental composition and mix proportioning to achieve the long-term durability in nuclear environment. Concrete elements may become radioactive through exposure to neutron radiation from the nuclear reactor. A selection of constituent materials of greatly reduced content of long-lived residual radioisotopes would reduce the volume of low-level waste during plant decommissioning. The objective of this investigation is an assessment of trace elements with a large activation cross section in concrete constituents and simultaneous evaluation of susceptibility of concrete to detrimental alkali-silica reaction. Two isotopes 60Co and 152Eu were chosen as the dominant long-lived residual radioisotopes and evaluated using neutron activation analysis. The influence of selected mineral aggregates on the expansion due to alkali-silica reaction was tested. The content of 60Co and 152Eu activated by neutron radiation in fine and coarse aggregates, as well as in four types of Portland cement, is presented and discussed in respect to the chemical composition and rock origin. Conflicting results were obtained for quartzite coarse aggregate and siliceous river sand that, despite a low content, 60Co and 152Eu exhibited a high susceptibility to alkali-silica reaction in Portland cement concrete. The obtained results facilitate a multicriteria selection of constituents for radiation-shielding concrete.

Relationship of Different Properties from Non-Destructive Testing of Heavy Concrete from Magnetite and Serpentinite.

Radiation-shielding concrete has been analyzed by several methods of destructive and non-destructive testing (NDT). Concretes made of crushed basalt, magnetite, serpentinite, and two different types of cement (Portland cement CEM I and slag cement CEM III/A) were studied. In this study, we analyzed concrete columns with a height of 1200 mm and a cross-section of 200 × 200 mm2. The top and bottom of the column were analyzed using data from compressive strength, dynamic modulus of elasticity, water penetration, and diffusion coefficients derived from the electrical resistivity test. This article presents the properties of fresh concrete and concrete after two years of setting. It was determined how the different ratios of basalt, magnetite, and serpentinite affect the individual measured parameters. Furthermore, correlation relations between individual resulting values were analyzed. It was observed that compressive strength generally does not correlate with other results. The diffusion coefficient correlated well with density and water penetration. Little or no correlation was observed in the diffusion coefficient with compressive strength and modulus of elasticity. The results of the study make it possible to refine the testing of heavy concretes in terms of electrical resistivity, and point to the possible use of NDT methods. The results also show which composition of heavy concrete is better in terms of effective diffusivity.

Formwork Pressure of a Heavyweight Self-Compacting Concrete Mix.

High-fluidity and self-compacting concrete (SCC) mixes were developed using special aggregates for radiation-shielding concrete. The special aggregates comprised heavyweight and hydrous aggregates (crushed magnetite, crushed serpentine, and their mixtures), which were selected to provide an enhanced attenuation of gamma and neutron radiation, respectively. For the mixed concrete design with a bulk density of up to 3570 kg/m3, two cement types were used: Portland cement CEM I and slag cement CEM III/A. The basic properties of the fresh self-compacting concrete were evaluated and the lateral formwork pressure exerted by the freshly mixed self-compacting concrete was measured and analyzed. An original test setup was developed for the determination of the lateral pressure on the square column formwork with pressure measurements carried out using six strain gauge pressure transducers, which was adequate for heavyweight concrete mixture testing. Self-compacting concrete mixtures containing a magnetite aggregate or blends of serpentine and magnetite aggregates with a slump flow of at least 550 mm were developed. The lateral pressure on the formwork was directly proportional to the density of the self-compacting heavyweight concrete mixes. The maximum values of the lateral pressure recorded in the test at a casting speed of 1.5 m/h did not exceed 27 kPa and 55% of hydrostatic pressure. Concrete mixtures with basalt, magnetite, and magnetite/serpentine blended aggregates were found to develop sufficient shear strength for proper stability during casting.

Physical, mechanical, and radiation attenuation properties of serpentine concrete containing boric acid

Serpentine and boric acid are effective materials to produce the radiation-shielding concrete (RSC) for attenuating the fast and thermal neutrons, respectively. Therefore, this study investigates the effect of boric acid (0, 1, and 3% by cement weight) on the physical, mechanical, microstructural, and radiation shielding properties of serpentine concrete. The results showed that the addition of boric acid hindered the hydration of cement through the generation of amorphous borate material, which encapsulates the cement phases and retards their transformation into hydration products. Such a retardation process negatively influenced the mechanical properties of boric acid-bearing concrete and contributed to the thicker and less condensed interfacial transition zone. Furthermore, unlike total γ-rays, boric acid enhanced the attenuation properties of serpentine concrete against thermal and fast neutrons favoring the former. There was a satisfying agreement between the theoretical and measured values of fast neutron attenuation parameters. However, negligible variations in the theoretical values of photon interaction parameters showed that porosity was the principal reason for the reduction in gamma-ray attenuation as a result of boric acid addition.

A review on sustainable utilization of industrial wastes in radiation shielding concrete

The increasing problem of industrial wastes' (IWs) accumulation and shortage of conventional construction materials such as aggregates can be simultaneously addressed by a careful selection and utilization of IWs in concrete. This paper targets an explicit assessment of the current status of utilization of various IWs in a particular type of concrete, namely, ‘Radiation Shielding Concrete (RSC)’. RSC is a high-density concrete which prevents any potential leakage of the X-rays, gamma rays, and fast-moving neutrons in various establishments such as nuclear power structures, X-ray or radiology department rooms in the hospitals. Traditionally, RSC has been made using high density natural aggregates like haematite, magnetite, or ilmenite, but this practice faces several challenges such as the NA being a limited resource, expensive, and non-available in several parts of the world. This paper reviews the research being carried out for the gainful utilization of various categories of IWs such as slags, supplementary cementitious materials, mines wastes, and a few miscellaneous IWs like polymers and glass, for a partial or complete replacement of conventional constituents of RSC for a greener construction.

Effect of elevated temperature on the mechanical properties and microstructure of heavy-weight magnetite concrete with steel fibers

In this study, the results of the physical and mechanical characterization of a high-density structural concrete for radiation shielding subjected to different intensities of thermal shock are analyzed. The concrete has been designed using high-density natural aggregates and steel reinforcing fibers, according to structural concrete requirements. The damage caused by high temperatures to concrete has been analyzed by residual physical, mechanical and microstructural characterization after thermal shock exposure. The analysis of the results allows us to determine the behavior and verify the integrity of the shielding concrete over the different temperature ranges.

New Concrete for Protection from Radiation in the Urals Based on Natural Fillers

The most difficult problem of the modern high-tech world is the protection of a living organism from the effects of radiation in the existence of nuclear technology in all areas of daily life. The article considers the problem of finding new effective building materials to protect people and the environment from the threat of the neutron and γ-radiation. Modern radiation-protective materials must have high strength and environmental characteristics of the performances and have a low cost. The authors carried out experimental studies on the development of a new radiation-shielding concrete using natural dunite aggregates from the Urals region. The research included selecting the original components of rational composition and technological characteristics of the concrete mixtures. The results showed its effectiveness compared to traditional granite aggregate used in concrete. On the experimental base of Ural Federal University named after. B.N. Yeltsin the research has shown an increase in efficiency of 1.35-3.0 times the effectiveness of the newly developed protection of electromagnetic radiation to protect against non-ionic and γ-excretions, depending on the energy field.