2006
DOI: 10.1016/j.nimb.2005.11.139
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Radiation transmission of concrete including boron waste for 59.54 and 80.99keV gamma rays

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Cited by 61 publications
(36 citation statements)
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“…On the other hand, Demir et al [6] have prepared the concrete specimens including borogypsum and colemanite concentrator wastes. They tested the differences in gamma rays passing energies for normal and boron waste (BW) additive concretes specimens.…”
Section: Boron Compounds (Bc) Such As Boric Acid (B[oh]mentioning
confidence: 99%
“…On the other hand, Demir et al [6] have prepared the concrete specimens including borogypsum and colemanite concentrator wastes. They tested the differences in gamma rays passing energies for normal and boron waste (BW) additive concretes specimens.…”
Section: Boron Compounds (Bc) Such As Boric Acid (B[oh]mentioning
confidence: 99%
“…The photon interaction with the matter depends on the incoming photon energy and the density of the shielding material [3,4]. A good shielding material should have high absorption cross-section for radiation and at the same time irradiation effects on its mechanical properties should be small [5]. The concrete shielding properties may vary depending on the material components of the 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%
“…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]. Due to its many versatile properties such as high melting point, low density, low thermal conductivity and high neutron absorption efficiency, B 4 C becomes an attractive absorber material [4] [ 8].…”
Section: Introductionmentioning
confidence: 99%