Development of special radiation shielding concretes using natural local materials and evaluation of their shielding characteristics

Kharita, M.H.; Takeyeddin, M.; Alnassar, Mohammad Saleh N; Yousef, S.

doi:10.1016/j.pnucene.2007.10.004

Cited by 133 publications

(48 citation statements)

References 1 publication

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“…As they occur relatively rarely, in comparison to other radiation, neutrons (especially these of high energy -fast ones) can penetrate very thick layers of materials [4]. Depending on the kinetic energy of neutrons (speed) and the type on nuclei there may occur different phenomena: scattering (elastic and inelastic), absorption (capture radiation (n, γ) or with charged particles emitted), the nuclear reaction (n, 2n) or (n, 3n) and the fission reaction.…”

Section: Neutron Transport Through a Concrete Membermentioning

confidence: 99%

“…This concept has been partially rejected by Kharita et al [4] who found that linear attenuation coefficients in the field of neutrons from Am-Be source for the heavyweight hematite concrete is about 10% higher than for concrete samples expected to be suitable for neutron shielding that was a concrete with high hydrogen content prepared with serpentine aggregate. Similar results were presented by Gallego et al [5] who analysed magnetite-based concrete and found its advantageous behaviour, when comparing neutron attenuation (B-14)…”

Section: Introductionmentioning

confidence: 99%

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Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

et al. 2015

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Concrete has been used as a shield against high-energy photons and neutrons since the beginning of use of nuclear reaction in energy, medicine and research. From that time the progress in concrete technology is huge -very good concrete used in 60's was about 30 MPa compressive strength, and now the recommendation of ETC-C is to use in EPR nuclear power plant the concrete at least class C45/55 for airplane resistant shell or class C40/50 for other structures. The Monte Carlo computer simulations indicate that an increase in density of the shielding member has a minor effect on the weakening of neutron transport and, therefore, the optimal composition of a shielding concrete against gamma radiation is different than the optimal composition of shielding concrete against neutron radiation. Neutron stopping is a two-step effect: slowing down of fast neutrons and absorption of thermal ones. Both result from the atomic composition of the barrier. The paper presents an analysis of neutrons transport through concrete cement mortar and polymer cement composites mortar based on specially designed experiments which allows for measuring fast neutron attenuation and thermal neutron capture separately. The aim of experiments was to find an influence of the cement type, polymer addition and moisture content on both aspects of neutron shielding properties of a composite. The experimental results were confirmed in MCNP simulations. There was found an influence of cement type on fast neutron attenuation due to differences in chemical composition. Next an important improvement of both fast neutron attenuation and thermal neutron capture due to polymer modification of concrete. The last was fond of clear linear relationship between fast neutron attenuation to the hydrogen content which shows the possibility of using this phenomenon in building material investigation like measurement of moisture content or polymer content in the polymer cement composites.

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Section: Neutron Transport Through a Concrete Membermentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

et al. 2015

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“…The concrete shielding properties may vary depending on the material components of the concrete. Aggregates are the largest constituent (about 70-80% of the total weight of normal concrete) [3,6]. The radiation shielding properties of concrete can be changed by adding different materials into concrete.…”

Section: Introductionmentioning

confidence: 99%

“…Addition of metal particles to concrete to enhance its density can be used for gamma and X-ray shielding purposes. There are many different theoretical and experimental studies working on improvement of concrete properties to suit the shielding requirements by means of photon attenuation coefficient [2,3,[5][6][7][8][9]. X-rays have three principal uses as diagnostic, therapeutic and in non medical radiographic devices.…”

Section: Introductionmentioning

confidence: 99%

Investigation of Shielding Performance of Concretes Produced with Iron Fillings Using Betatron X-Ray Radiography

et al. 2016

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One of the most widely used structural materials in radiation shielding is concrete. Addition of metal particulates to concrete to enhance its density can be used for gamma and X-ray shielding purposes. In this study radiation shielding performance of concrete containing different amounts of iron filling were evaluated using Betatron X-ray radiation source. For this purpose concretes were produced by adding iron filling in the ratios of 0%, 10%, 20%, 30% (in weight) to the cement. CIT/7.5 Betatron source which is a compact, circular electron accelerator, generating directional X-ray beam, was used in this study. Experiments were performed by using conventional radiography test. The results were compared with results for normal concrete. It was observed that the film density differences between the iron filling and normal concrete are in the range of about 10-60%.

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“…We can distinguish two basic categories of radiation: ionizing and non-ionizing ones. Ionizing radiation carried by quanta of large energy can change the structure of irradiated matter, even hurting people causing chemical, biological changes in human body [1][2][3][4][5][6]. Non-ionizing radiation does not cause microscopic damage, but some types can cause chemical changes or get human body warm.…”

Section: Introductionmentioning

confidence: 99%

Performance of Boron-Carbide as Radiation Shielding

et al. 2015

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Radiation is widely used many fields, especially in medical science. The shielding is the basic method of protection against unnecessary influence of radiation. One of the tools most commonly used in nuclear medicine is vial pig container. Usually lead is used as shielding material in vial pigs to cover radiation source, such as Tc 99m which is the most widely used radiopharmaceutical in nuclear medicine. In this study boron carbide has been tested as an substitute of lead in vial pig. The measurement has been performed with the Geiger-Müller counter and the personal combined radiation detectors.

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Development of special radiation shielding concretes using natural local materials and evaluation of their shielding characteristics

Cited by 133 publications

References 1 publication

Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

Investigation of Shielding Performance of Concretes Produced with Iron Fillings Using Betatron X-Ray Radiography

Performance of Boron-Carbide as Radiation Shielding

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