Radiation Shielding Properties Prediction of Barite used as Small Aggregate in Mortar

Construction materials used in the nuclear industry used to be mainly heavy materials, including lead plates, radiation-resistant heavy concrete, etc. However, these materials are either toxic after a long time of use (lead) or difficult to construct (radiation-resistant heavy concrete) and their cost is rather high. Therefore, there is a need for the manufacturing of a new kind of material with good radiation resistance, which is light, easy to use, and costs less. Barium is less toxic and more cost-effective than lead. Due to the importance of barium compounds in radiation shielding, the study of gamma radiation interactions within these compounds becomes essential, so the most important part of such a study is the experimental one, which shows the effect of the barite powder in the radiation resistance of the mortar. The research results show that the higher the thickness and percentage of barite powder, the higher is the radiation resistance.

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On the necessity and the role of descriptors of neutron activated structural and shielding materials of nuclear installations for future decommissioning

Nuclear Energy and Technology ◽

10.3897/nucet.4.31875 ◽

2018 ◽

Vol 4 (4) ◽

pp. 257-262 ◽

Cited By ~ 1

Author(s):

Igor Engovatov ◽

Boris Bylkin ◽

Alexey Kozhevnikov ◽

Dmitry Sinyushin

Keyword(s):

Neutron Transport ◽

Irradiation Time ◽

Construction Materials ◽

Structural Materials ◽

Radiation Shielding ◽

Radioactive Wastes ◽

Nuclear Industry ◽

Activation Technique ◽

Reactor Unit ◽

Materials Used

Existing situation in nuclear industry is characterized with simultaneous development of the following two processes: design and construction of new generation of nuclear installations and decommissioning of installations of older generations. Significant amounts of radioactive wastes generated during the decommissioning phase are determined both for the first and the second types of installations by the induced activity of neutron irradiated structural and shielding materials. Concentration of the so-called radioactivity-hazardous nuclides in primary building and construction materials is the most important characteristics determining the resulting levels of induced activity. Values of these concentrations for the same type of material extracted from different geological deposits may differ by one or two orders of magnitude. Information about concentrations of radiation-hazardous elements in radiation shielding materials is fragmented and, as a rule, unsuitable for practical application. The purpose of the present study was to substantiate the necessity of compiling and recording the data on the concentrations of radioactivity-hazardous nuclides for building and structural materials for nuclear installations during the phases of design, operation and decommissioning. Three types of shielding concrete compositions were selected for the investigation. Concentrations of radioactivity-hazardous nuclides were mainly obtained by neutron activation technique. Neutron transport calculations were performed in one-dimensional cylindrical geometry at the core mid-plane according to usual core-vessel-shielding model of modern VVER reactor unit including 2-m thick concrete shield. Both transport and activation calculations were undertaken using modules of SCALE system. The obtained results allow estimating neutron-induced activation levels in the material as the function of irradiation time, amounts and categories of radioactive waste and their evolution during the decay time from 1 to 100 years. It was established that neutron-induced activity of shielding concrete strongly depends on the actual concentrations of radioactivity-hazardous nuclides in the concrete including ‘trace’ concentrations (other factors being the same). It was also shown that failure to take such concentrations into account may lead to the underestimation of neutron-induced activation levels and amounts of radioactive wastes and their category. The obtained results confirmed the necessity of compiling and maintaining data records on the concentrations of radioactivity-hazardous nuclides for materials used in structural and shielding materials of nuclear installations. Proposals were formulated on the potential accumulation of information, composition and formatting of descriptors of chemical composition of shielding and structural materials of nuclear installations.

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Bismuth modified gamma radiation shielding properties of titanium vanadium sodium tellurite glasses as a potent transparent radiation-resistant glass applications

Nuclear Engineering and Technology ◽

10.1016/j.net.2020.10.006 ◽

2020 ◽

Author(s):

M.H.M. Zaid ◽

K.A. Matori ◽

H.A.A. Sidek ◽

I.R. Ibrahim

Keyword(s):

Gamma Radiation ◽

Radiation Shielding ◽

Tellurite Glasses ◽

Sodium Tellurite ◽

Radiation Resistant ◽

Shielding Properties ◽

Titanium Vanadium

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New Composite Material Based on Heavy Concrete and Basalt-Boron Fiber for Neutron Radiation Shielding Properties

Nuclear and Radiation Safety ◽

10.32918/nrs.2019.2(82).04 ◽

2019 ◽

pp. 19-25 ◽

Cited By ~ 1

Author(s):

I. Romanenko ◽

M. Holiuk ◽

A. Nosovsky ◽

T. Vlasenko ◽

V. Gulik

Keyword(s):

Composite Material ◽

Neutron Radiation ◽

Radiation Shielding ◽

Nuclear Industry ◽

Protective Properties ◽

Horizon 2020 ◽

Boron Fiber ◽

Fast Fission ◽

Fission Neutrons ◽

Shielding Properties

It is necessary to have reliable radiation protection for safe operation of different radiation sources. Radiation shielding properties have been studied for a long time both in our country and abroad. However, there is a strong necessity to develop new composite materials, which will provide protection against radiation and have improved mechanical and economic characteristics. The paper describes a new composite material for neutron radiation shielding properties based on heavy concrete with serpentinite aggregate and with basalt-boron fiber with different concentrations of fiber boron oxide for using in biological shielding in nuclear industry. Protective properties of the new composite material were investigated with different neutron sources: 1) neutrons with 14 MeV energy; 2) fast fission neutrons for U-235; 3) fast fission neutrons for U-235 after passing a water layer. The simulation of the neutron radiation in presented composite material with adding crushed stone aggregate and serpentinite aggregate is performed by Monte Carlo Serpent code. It is shown that basalt-boron fibers in concrete improve the protective properties of concrete against neutron irradiation for neutrons with different energies, but the most effective is the addition of a basalt-boron fiber in the case of thermal neutrons. This research was supported by Horizon 2020 ERA-NET Support Programme, Research Grant Agreement No 7.9-3/18/7 (“Development of Boron-Infused Basalt-Fiber Reinforced Concrete for Nuclear and Radioactive Waste Management Applications”). Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a joint programme of the members of the EUROfusion consortium (2014-2020), Work Package PMI. Also, this research was carried out with the financial support of the IAEA, within the terms and conditions of the Research Contract20638 in the framework of the Coordinated Research Project (CRP) “Accelerator Driven Systems (ADS) Applications and Use of Low-Enriched Uranium in ADS (T33002)’’ within the Project “The Two-Zone Subcritical Systems with Fast and Thermal Neutron Spectra for Transmutation of Minor Actinides and Long-Lived Fission Products”.

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Spectral, Radiation-Optical and Shielding Properties of Phosphate Glasses with High Lead Content

Advanced Materials Research ◽

10.4028/www.scientific.net/amr.39-40.213 ◽

2008 ◽

Vol 39-40 ◽

pp. 213-218 ◽

Cited By ~ 4

Author(s):

Valerii I. Arbuzov ◽

Yurii K. Fyodorov

Keyword(s):

Radiation Shielding ◽

Phosphate Glasses ◽

Lead Content ◽

Glass Layer ◽

Similar Data ◽

Spectral Radiation ◽

Radiation Resistant ◽

Shielding Properties ◽

High Lead ◽

Thick Glass

Spectral, radiation optical, and radiation shielding properties of new phosphate glasses, TPF, with high lead content (up to 40 mol. % PbO) were studied. They are characterized by the heightened radiation optical resistance at exposure doses up to 5*107 R, and by the improved radiation shielding properties as compared with similar data of silicate glasses with the same lead content. A TPF boundary of semi-transmission for a 1 cm thick glass layer lies approximately at 355 nm, its absorption coefficient, µ, for γ-quanta of 137Cs (0.663 MeV) and 60Co (1.25 MeV) reach 0.373 and 0.240 cm-1 whereas µ’s of the Russian radiation resistant strong flint TF110 (40 mol. % PbO) are equal to 0.355 and 0.214 cm-1. These properties allowed to use TPF instead of strong silicate flints as material for observation radiation schielding windows of facilities of special usage.

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ACCELERATOR-BASED TESTS OF RADIATION SHIELDING PROPERTIES OF MATERIALS USED IN HUMAN SPACE INFRASTRUCTURES

Health Physics ◽

10.1097/01.hp.0000288560.21906.4e ◽

2008 ◽

Vol 94 (3) ◽

pp. 242-247 ◽

Cited By ~ 33

Author(s):

C Lobascio ◽

M Briccarello ◽

R Destefanis ◽

M Faraud ◽

G Gialanella ◽

...

Keyword(s):

Radiation Shielding ◽

Properties Of Materials ◽

Shielding Properties ◽

Materials Used

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Study of capability of microorganisms to develop on construction materials used in space objects.

57th International Astronautical Congress ◽

10.2514/6.iac-06-a1.p.2.06 ◽

2006 ◽

Author(s):

Mrs. Yulia Svistunova

Keyword(s):

Construction Materials ◽

Space Objects ◽

Materials Used

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Influence of heavy metal oxides to the mechanical and radiation shielding properties of borate and silica glass system

Journal of Materials Research and Technology ◽

10.1016/j.jmrt.2021.01.117 ◽

2021 ◽

Vol 11 ◽

pp. 1322-1330

Author(s):

M.H.M. Zaid ◽

H.A.A. Sidek ◽

K.A. Matori ◽

A. Abdu ◽

K.A. Mahmoud ◽

...

Keyword(s):

Heavy Metal ◽

Metal Oxides ◽

Silica Glass ◽

Radiation Shielding ◽

Glass System ◽

Shielding Properties ◽

Heavy Metal Oxides

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Double-layered fiber for lightweight flexible clothing providing shielding from low-dose natural radiation

Scientific Reports ◽

10.1038/s41598-021-83272-3 ◽

2021 ◽

Vol 11 (1) ◽

Author(s):

Seon-Chil Kim ◽

Jun Sik Son

Keyword(s):

Low Dose ◽

Layered Composite ◽

Radiation Shielding ◽

Flight Attendants ◽

Low Dose Radiation ◽

Natural Radiation ◽

Composite Yarn ◽

Materials Used ◽

Fiber Fabric ◽

Dose Radiation

AbstractNatural and medical radiation are the most frequent sources of daily low-dose radiation exposure for the general public, but these radiation levels are generally acceptable. Among various occupations, aviation crew members and medical workers are exposed to high levels of radiation from scattered rays. This study focused on developing clothing for shielding aviation crew members from natural radiation during air travel. Materials were selected considering their radiation-shielding properties. A tungsten double-layered composite yarn and a polyethylene terephthalate (PET) fiber fabric containing BaSO4 were manufactured. The characteristics and shielding performances of the products were analyzed. Prototypes of a protective scarf (for shielding the thyroid gland) and apron (for shielding the torso) for flight attendants were produced. A lightweight fabric was produced that neither restricts the movement of the wearer nor causes them skin discomfort. The shielding performances of the tungsten composite and PET fiber fabrics containing BaSO4 were 0.018 mmPb and 0.03 mmPb, respectively, demonstrating low-dose shielding that may be useful for protecting aviation crew members from scattered rays. The characteristics of the developed fibers are comparable to those of materials used in clothing production; therefore, low-dose radiation-shielding clothing could be manufactured for use in aviation, medical, and other industries.

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