Preparation, shielding properties and mechanism of a novel neutron shielding material made from natural Szaibelyite resource

Dong, Mengge; Xue, Xiangxin; Li, Zhefu; He, Yang; Sayyed, M.I.; Elbashir, B.O.

doi:10.1016/j.pnucene.2018.03.010

Cited by 22 publications

(5 citation statements)

References 27 publications

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“…In previous studies, the shielding properties of the investigated materials have been calculated or/and measured, for specific neutron energies or incident neutrons in a specific energy range (the range of fast neutrons, intermediate energy neutrons, or/and the range of slow neutrons). There are also studies of radiation shielding in which the energy of neutrons from radioactive sources has been used as average energy [2,4,5,[7][8][9] and [19][20][21][22][23][24][25][26][27]. Additionally, in many studies, the macroscopic cross-section area of shielding materials was calculated as an approximate value in the neutron energy range of 2 to 12 MeV [5,10,18,[27][28][29][30][31] depending on Wood and Kaplan publications [32,33].…”

Section: Introductionmentioning

confidence: 99%

“…There are also studies of radiation shielding in which the energy of neutrons from radioactive sources has been used as average energy [2,4,5,[7][8][9] and [19][20][21][22][23][24][25][26][27]. Additionally, in many studies, the macroscopic cross-section area of shielding materials was calculated as an approximate value in the neutron energy range of 2 to 12 MeV [5,10,18,[27][28][29][30][31] depending on Wood and Kaplan publications [32,33]. Previous studies confirm the existence of deficiencies in the study of the performance of materials as shields for neutrons because they did not achieve a wide range of neutron energies.…”

Section: Introductionmentioning

confidence: 99%

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Evaluation of neutron shielding performance for some alloys

Reda¹,

El²

2021

Phys. Scr.

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Alloys, in general, and stainless steel, in particular, are among the basic materials for shielding against nuclear radiation. Some selected alloys among a lot of shielding materials in numerous literature were investigated as shielding materials against neutrons in a wide neutron energy range of 10−5 eV to 20 MeV. The neutron mass attenuation coefficient (NMAC) for the materials under investigation was calculated using the Monte Carlo N-Particle transport code, version 5 (MCNP5). The results indicate that the alloys under investigation have a good shielding performance against neutrons along the studied neutron energy range especially 5% B4C (S8) alloy. The 5% B4C sample shows a high shielding performance for neutrons of energy < 1.6 x 10-3 MeV as compared to the other investigated alloys. While the stainless steel 316 (S3) shows the best shielding performance for neutrons of energies > 0.2 MeV. The study also shows that the alloy must contain a percentage of a light element that has a high ability to absorb slow neutrons such as boron. This study is useful in selecting the appropriate shielding material for specific neutron energies. MCNP5 calculations were confirmed by comparing its results for iron with the corresponding evaluated data ENDF/B-V extracted from International Atomic Energy Agency (IAEA) database.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Evaluation of neutron shielding performance for some alloys

Reda¹,

El²

2021

Phys. Scr.

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“…One approach is the addition of metal that can improve its toughness and greatly increase its application range (12)(13)(14). Among other things, the composite material of boride, combined with plastic or aluminum, produces an effective neutron shielding material (15)(16)(17)(18)(19). Among them, titanium diboride (TiB2) not only has the properties of high melting point (20,21), high hardness (22)(23)(24), and good high-temperature mechanical properties (25,26), but it also has good oxidation resistance (27,28), strong resistance to chemical corrosion and molten metal corrosion (29,30), and can resist the corrosion of non-alkali molten salts (31)(32)(33)(34).…”

Section: Introductionmentioning

confidence: 99%

Research on Thermal Neutron Shielding Performance of TiB2-Al Composite Materials

Wang

Li²,

Dong³

et al. 2021

Preprint

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Although the various excellent properties and preparation methods of TiB2-based composites have been extensively studied, their neutron shielding properties have not received as much attention. In this article, the neutron shielding performance of the previously prepared TiB2-Al composite will be studied. The photo neutron source device was used to carry out neutron irradiation tests on test samples with a thickness of 10 mm. The average thermal neutron shielding rate of TiB2-based boron-containing composites is 17.55%, and the shielding rate increases with the increase of BN content. The macroscopic cross-section of thermal neutrons of the composites generally shows a stable trend, and when the BN content is 10%, the thermal neutrons macroscopic cross section reaches the maximum value of 7.58cm-1. With the increase of the BN content, the thermal neutron fluence rate shows a gradually decreasing trend.

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“…Neutron radiation generated by nuclear reactors and accelerators poses a huge threat to humans and electronic components as it can strongly penetrate biological bodies and electronic devices [5]. Traditional neutron shielding materials include concrete and water, in which concrete possesses better shielding properties [6][7][8], but is not convenient for moving from one spot to another. By comparison, water contains H, which makes it an excellent neutron attenuation body, but might negatively impact the overall mechanical properties.…”

Section: Introductionmentioning

confidence: 99%

Neutron Shielding Performance of 3D-Printed Boron Carbide PEEK Composites

Cao

et al. 2020

Materials

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Polyethylene is used as a traditional shielding material in the nuclear industry, but still suffers from low softening point, poor mechanical properties, and difficult machining. In this study, novel boron carbide polyether-ether-ketone (PEEK) composites with different mass ratios were prepared and tested as fast neutron absorbers. Next, shielding test pieces with low porosity were rapidly manufactured through the fused deposition modeling (FDM)-3D printing optimization process. The respective heat resistances, mechanical properties, and neutron shielding characteristics of as-obtained PEEK and boron carbide PEEK composites with different thicknesses were then evaluated. At load of 0.45 MPa, the heat deformation temperature of boron carbide PEEK increased with the boron carbide content. The heat deformation temperature of 30% wt. boron carbide PEEK was recorded as 308.4 °C. After heat treatment, both tensile strength and flexural strength of PEEK and PEEK composites rose by 40%–50% and 65%–78%, respectively. Moreover, the as-prepared composites showed excellent fast neutron shielding performances. For shielding test pieces with thicknesses between 40 mm and 100 mm, the neutron shielding rates exhibited exponential variation as a function of boron carbide content. The addition of 5%–15% boron carbide significantly changed the curvature of the shielding rate curve, suggesting an optimal amount of boron carbide. Meanwhile, the integrated shielding/structure may effectively shield neutron radiation, thereby ensuring optimal shielding performances. In sum, further optimization of the proposed process could achieve lightweight materials with less consumables and small volume.

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Preparation, shielding properties and mechanism of a novel neutron shielding material made from natural Szaibelyite resource

Cited by 22 publications

References 27 publications

Evaluation of neutron shielding performance for some alloys

Evaluation of neutron shielding performance for some alloys

Research on Thermal Neutron Shielding Performance of TiB2-Al Composite Materials

Neutron Shielding Performance of 3D-Printed Boron Carbide PEEK Composites

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