Influence of magnetite and boron carbide on radiation attenuation of cement–fiber/composite

Abdo, A. El‐Sayed; Ali, Magdy A. M.; Ismail, M. R.

doi:10.1016/s0306-4549(02)00074-9

Cited by 19 publications

(8 citation statements)

References 8 publications

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“…In most cases, good agreement can be noticed between the determined values by the proposed method and the traditional method. Besides, the determined Σ R , µ R and Z eff for these materials along with those shown in Figure 2 were used to determine Σ R , µ R for natural Fiber-Plastic (FP), Fiber-Plastic-Lead (FPPb), Cement-Fiber (CF) and Cement-Fiber-Magnetite (CFM) composites, along with the shielding materials of dolomite-sand, barite-barite, magnetite-limonite, ilmenite-ilmenite [22][23][24]. The chemical compositions shown in Table 2 were taken from references [22][23][24].…”

Section: Resultsmentioning

confidence: 99%

A Method for Simultaneous Determination of Effective Removal Cross-section for Fast Neutrons and Mass Absorption Coefficient for Gamma Rays

Elkady¹

2014

SOJMSE

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A method for determining the effective removal cross section (∑ R ) of fast neutrons and mass absorption coefficient (µ R ) for gamma rays at energies 661.6 keV and 1332.5 keV is proposed. It is based on relating the ratio (R) of ∑ R to µ R at 661.6 keV and 1332.5 keV to effective atomic number (Z eff ) for elements, compounds, composite materials and alloys. It is shown that the R-values versus Z eff for the most studied materials lie on two master curves. The method was tested by determining ∑ R and µ R for several materials. There is a good agreement between results obtained from the present developed method and the traditional method. Some deviations from the values obtained from the traditional method are discussed as well.

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Section: Resultsmentioning

confidence: 99%

A Method for Simultaneous Determination of Effective Removal Cross-section for Fast Neutrons and Mass Absorption Coefficient for Gamma Rays

Elkady¹

2014

SOJMSE

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“…Dry cement powder reacts with water to form the binder, and the mix ratio between the cement and water defines the water-to-cement ratio, which influences the concrete strength. The amount of cement used in research ranges from 269–1423 kg per cubic meter (kg/m 3 ) of concrete produced [ 63 , 64 ]. The amount of cement used can affect the matrix of concrete, hence influencing the mechanical properties of the concrete.…”

Section: Alternative Materials Used In Rscmentioning

confidence: 99%

“…It has been used to form shielding material by adding lead oxide or lead ore mineral to the elastomer matrix [ 168 , 169 ]. Recent research has used SBR as a 10–20% cement replacement to increase the amount of hydrogen in concrete [ 13 , 64 ]. Concrete with a 15% SBR replacement of cement resulted in a maximum ∑ R (E n ) value of 0.09 cm −1 [ 13 ].…”

Section: Radiation Shieldingmentioning

confidence: 99%

“…Another type of boron source, which is boron carbide, also achieved improved neutron shielding with its presence. An 11.43% addition of boron carbide of the overall magnetite concrete weight resulted in a 20% increase of the ∑ R of fast neutrons to 0.128 cm −1 [ 64 ]. In terms of the slow neutron cross section, magnetite concrete with boron carbide recorded a ∑ R of 0.196 cm −1 , which is a 35% increment compared with that of normal concrete.…”

Section: Radiation Shieldingmentioning

confidence: 99%

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

et al. 2022

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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.

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“…Boron carbide is frequently used as a shielding material, either alone or combined with other material for radiation shielding [6]. B 4 C is used extensively in nuclear reactors as a neutron absorber [4] and as a constituent material of neutron shields because of its high absorption of neutrons [7].…”

Section: Introductionmentioning

confidence: 99%

Preliminary study of neutron absorption by concrete with boron carbide addition

Abdullah

Ariffin

Hamid

et al. 2014

AIP Conference Proceedings

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New shielding material development for compact accelerator-driven neutron source AIP Advances 7, 045213 (2017) . Concrete has become a conventional material in construction of nuclear reactor due to its properties like safety and low cost. Boron carbide was added as additives in the concrete construction as it has a good neutron absorption property. The sample preparation for concrete was produced with different weight percent of boron carbide powder content. The neutron absorption rate of these samples was determined by using a fast neutron source of Americium-241/Be (Am-Be 241) and detection with a portable backscattering neutron detector. Concrete with 20 wt % of boron carbide shows the lowest count of neutron transmitted and this indicates the most neutrons have been absorbed by the concrete. Higher boron carbide content may affect the concrete strength and other properties.

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Influence of magnetite and boron carbide on radiation attenuation of cement–fiber/composite

Cited by 19 publications

References 8 publications

A Method for Simultaneous Determination of Effective Removal Cross-section for Fast Neutrons and Mass Absorption Coefficient for Gamma Rays

A Method for Simultaneous Determination of Effective Removal Cross-section for Fast Neutrons and Mass Absorption Coefficient for Gamma Rays

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

Preliminary study of neutron absorption by concrete with boron carbide addition

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