Finding a suitable shield for mixed neutron and photon fields based on an Am–Be source

Karimi-Shahri, Keyhandokht; Rafat-Motavalli, Laleh; Hakimabad, Seyyed Hashem Miri

doi:10.1007/s10967-012-2225-9

Cited by 15 publications

(10 citation statements)

References 15 publications

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“…[32][33][34][35] Researches have been carried out to reduce the thickness of the concrete as much as possible by adding boronized polyethylene and borax in order to improve the quality of the shielding and it has been determined that the total activity level of the concrete has been significantly reduced. 33,[36][37][38][39][40][41] O) to the material does not have much influence on the durability of concrete, but it has crucial influences on the efficiency of thick concrete armors, as it provides up to 80% better absorption than concretes that cannot catch gamma rays. [39][40][41] Blending the basic materials in the concrete structure with mineral contributions in various proportions causes changes in attenuation parameters such as the effective atomic number, linear and mass attenuation coefficients of the concrete for gamma rays and neutrons.…”

Section: Introductionmentioning

confidence: 99%

“…In recent years, a lot of research has been done to build up an advanced kind of concrete by modification the properties of alternative materials and cement 32‐35 . Researches have been carried out to reduce the thickness of the concrete as much as possible by adding boronized polyethylene and borax in order to improve the quality of the shielding and it has been determined that the total activity level of the concrete has been significantly reduced 33,36‐41 . Supplementation of borax (Na 2 [B 4 O 5 (OH) 4 ]8H 2 O) to the material does not have much influence on the durability of concrete, but it has crucial influences on the efficiency of thick concrete armors, as it provides up to 80% better absorption than concretes that cannot catch gamma rays 39‐41 .…”

Section: Introductionmentioning

confidence: 99%

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Gamma irradiation, thermal conductivity, and phase change tests of the cement‐hyperbranched poly amino‐ester‐block‐poly cabrolactone‐polyurathane plaster‐lead oxide and arsenic oxide composite for development of radiation shielding material

Cinan

Baskan

Erol

et al. 2021

Intl J of Energy Research

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Summary The work which has been done on cement‐polymer composite based shielding materials was comprehensively described in the present article, the choice of the study presented here is based on the choice of the researches. The new Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane Plaster‐concrete composites mixed with different percentage soft lead oxide and arsenic oxide is used to research gamma‐ray shielding and thermal conductivity characteristics. The synthesis of new Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane copolymer was achieved by Atom Transfer Reaction and Condensation Polymerization methods. The characterization of Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane Plaster was made with the Nuclear Magnetic Resonance, Fourier Transform Infrared Spectroscopy, Differential Scanning Calorimetry, Gel Permeation Chromatography, Thermogravimetric Analysis, Scanning Electron Microscope methods. The transmitted fluxes of gamma‐rays that were emitted from Eu152 source was detected by a High Purity Germanium (HPGe) detector system at Karadeniz Technical University‐Department of Physics in Trabzon and analyzed by a GammaVision (Version:6.07‐Ortec, Oak Ridge, TN) computer program. The composite phase change materials including 89, 87, 69, 67% Portland cement, 1% and 3% PU‐Plaster, 10% and 30% weight percent lead oxide and arsenic oxide was irradiated in the various gamma ray photon energy region (121.78, 344.28, 778.90, 964.08, 1085.87, 1112.07, and 1408.01 keV) for 3600 seconds. Then, linear attenuation coefficients, mass attenuation coefficients, half‐value layer, tenth value layer, mean free path, radiation protection efficiency, and gamma‐rays absorption of concrete‐the Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane copolymers specimens were experimentally investigated. Thermal properties and morphological analysis of the irradiated substances were explored handling differential scanning calorimetry, thermogravimetric analysis, and scanning electron microscope methods of the nano lead oxide and arsenic oxide including composite phase change material via gamma irradiation were submitted. Moreover, the effect of the Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane amount on the radiation attenuation of the composite material was investigated. Gamma attenuation experiments have been performed to specify lead equivalent values for the improved composite material. The composite equivalent thickness values from 0.5 to 0.6 cm sample thickness and 0.665 cm radius were obtained. Via crosschecking the acquired data from concrete samples with and without lead and arsenic, it was observed that, if the powder of lead oxide and arsenic oxide to cement ratio of 10% and 30% by weight is added in the concrete mixture, the concrete‐the Hyperbranched Poly Amino‐Ester‐block‐Poly Caprolactone‐Polyurathane composite can be used as a suitable shield against gamma rays. Also, mass attenuation coefficients were calculated as theoret...

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Gamma irradiation, thermal conductivity, and phase change tests of the cement‐hyperbranched poly amino‐ester‐block‐poly cabrolactone‐polyurathane plaster‐lead oxide and arsenic oxide composite for development of radiation shielding material

Cinan

Baskan

Erol

et al. 2021

Intl J of Energy Research

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“…The use of colemanite concrete proved to be an easier and more effective solution than distributing gamma shields (e.g. lead blocks) within neutron absorbing materials, such as paraffin [22][23]. In presence of high-energy gamma-and X-ray sources, the lower atomic number of elements constituting colemanite concrete represents a further advantage with respect to lead shields, in particular in the pair production and Compton scattering regions [17,24].…”

Section: Introductionmentioning

confidence: 99%

Thermal stability and high-temperature behavior of the natural borate colemanite: An aggregate in radiation-shielding concretes

Lotti

Comboni

Gigli

et al. 2019

Construction and Building Materials

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Colemanite is a natural borate that can be used as an aggregate in neutron-radiation shielding concretes. In this study, we report its thermal behavior, up to 500°C, by describing: 1) its dehydration mechanisms and 2) its thermo-elastic parameters. The thermal expansion of colemanite is significantly anisotropic. The refined volume thermal expansion coefficient at ambient conditions is: V0 = 4.50(10)10-5 K-1. The loss of structural H2O occurs at least from ~ 240 °C and at T > 325 °C, an irreversible amorphization occurs, followed by a complete dehydration. The potential implications on the use of colemanite as concrete-aggregate are discussed.

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“…Te suitability of hydrogen as a moderator makes any material with a high content of hydrogen a good candidate for shielding of a 241 Am-Be source. In order to provide suitable as well as adequate shielding for photons, materials are chosen according to their linear attenuation coefcient and mass density [2].…”

Section: Introductionmentioning

confidence: 99%

Effectiveness of Serpentine Concrete as Shielding Material for Neutron Source Facility Using Monte Carlo Code

Abrefah

Tuffour-Achampong

Amoah

2023

Science and Technology of Nuclear Installations

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In recent years, much attention has been dedicated to finding techniques to reduce exposure doses. This work examines the effectiveness of using serpentine concrete to shield a neutron source using a 241Am-Be neutron source facility at the National Nuclear Research Institute (NNRI) as a case study. The results obtained for both neutrons and gamma indicate that serpentine concrete provides better shielding as compared to ordinary concrete. At a distance of 100 cm from the Am-Be source, when shielded with serpentine concrete, it was found that personnel will receive an average gamma dose of 4.395.395 ± 0.122 μSv/h while a dose of 10.399 ± 0.083 μSv/h will be received for ordinary concrete shield. The average neutron dose equivalent at 100 cm, for ordinary concrete and serpentine concrete were 32.189 ± 0.277 and 9.276 ± 0.505, respectively. All dose equivalents obtained were also within internationally accepted limits.

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Finding a suitable shield for mixed neutron and photon fields based on an Am–Be source

Cited by 15 publications

References 15 publications

Gamma irradiation, thermal conductivity, and phase change tests of the cement‐hyperbranched poly amino‐ester‐block‐poly cabrolactone‐polyurathane plaster‐lead oxide and arsenic oxide composite for development of radiation shielding material

Gamma irradiation, thermal conductivity, and phase change tests of the cement‐hyperbranched poly amino‐ester‐block‐poly cabrolactone‐polyurathane plaster‐lead oxide and arsenic oxide composite for development of radiation shielding material

Thermal stability and high-temperature behavior of the natural borate colemanite: An aggregate in radiation-shielding concretes

Effectiveness of Serpentine Concrete as Shielding Material for Neutron Source Facility Using Monte Carlo Code

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