Shielding characteristics of polymer-based concretes in neutron-radiation fields

Belyakov, V.V.; Grigor'ev, V. A.; Козлов, В. В.; Lavdanskii, P.A.; Nazarov, V. M.; Remeiko, O. A.

doi:10.1007/bf01117999

Cited by 12 publications

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“…Concerning that introduce up to 300 kg/m 3 of polyethylene filler into PCC is effective in physicomechanical and technicoeconomic aspects it was proved that PCC can have a comparatively easily adjusted hydrogen content (up to 60 kg/m 3 ) and their principal shielding characteristics in fields of neutron radiation with E < 10 MeV are nearly exponentially dependent on the hydrogen content in the concrete [11]. Than a nomogram for comparative calculation of thickness of technological shielding against radiations from reactor spectra depending on hydrogen content in concrete of density 2000-2400 kg/m 3 has been drawn [12]. Analysis of the nomograms shows that the use of PCC allows the thickness of the shielding to be reduced by 30-40% in comparison with that required with reference cement concrete with a hydrogen content of 6 kg/m 3 .…”

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confidence: 99%

Polymers in Concrete – The Shielding against Neutron Radiation

Piotrowski

Tefelski

Mazgaj

et al. 2015

AMR

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Concrete has been used as a shield against high-energy photons (gamma) and neutrons since the beginning of use of nuclear reaction in energy, medicine and research. State of knowledge in shielding concrete technology is that while in case of protection against gamma radiation an increase in density caused by change of aggregate type for heavy-weight one is usually an efficient solution, the protection against neutrons is more complex. It is due to the differences in interactions of neutrons with the matter, depending on their kinetic energy and cross-sections for different reactions of the component atoms of the cement paste and the aggregate. The paper presents the results of the project NGS-Concrete - New-Generation Shielding Concrete. The aim is to design the composition of concrete against ionizing radiation, achieved by the use of experiment based on multi-criteria optimization of materials supported by the Monte Carlo simulations. Better concrete is the one that absorbs more thermal neutrons and slows down more fast neutrons at the same time. In the paper both results of Monte Carlo simulations and experimental studies on ordinary and heavyweight concrete containing epoxy polymer additive are presented. Close values of thermal neutron attenuation coefficients proved good accordance between simulation and experiment. The final conclusion is that epoxy resin is an efficient additive for neutron shielding concretes improving its ability to protect mainly against low energy neutrons. In experimental measurement there has not been observed an improvement of fast neutron attenuation due to increase of hydrogen atom content introduced with epoxy.

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confidence: 99%

Polymers in Concrete – The Shielding against Neutron Radiation

Piotrowski

Tefelski

Mazgaj

et al. 2015

AMR

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“…Since the 1970s, various special composite shielding materials have been developed. Those materials are usually made of organic polymer materials as base-materials and filled with a ray-absorptive substance [6]. In recent years, heavy metal particles, such as lead based materials, have also been filled into organic polymer base-materials as functional components to synthesize γ-ray shielding composites [7,8].…”

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confidence: 99%

Numerical simulation and experimental study of PbWO ₄ /EPDM and Bi ₂ WO ₆ /EPDM for the shielding of γ -rays

et al. 2016

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Abstract:The MCNP5 code was employed to simulate the γ-ray shielding capacity of tungstate composites. The experimental results were applied to verify the applicability of the Monte Carlo program. PbWO4 and Bi2WO6 were prepared and added into ethylene propylene diene monomer (EPDM) to obtain the composites, which were tested in the γ-ray shielding. Both the theoretical simulation and experiments were carefully chosen and well designed. The results of the two methods were found to be highly consistent. In addition, the conditions during the numerical simulation were optimized and double-layer γ-ray shielding systems were studied. It was found that the γ-ray shielding performance can be influenced not only by the material thickness ratio but also by the arrangement of the composites.

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“…The possibility of improving neutron shielding properties of concrete by polymer addition has already been presented in 70's by Belyakov et al [6,7]. New approach in this field was presented by Malkapur et al [8] in study on the effect of mix parameters and hydrogen loading on the neutron radiation shielding characteristics of latex modified concrete mixes.…”

Section: Introductionmentioning

confidence: 99%

NGS-Concrete - New Generation Shielding Concrete against Ionizing Radiation - the Potential Evaluation and Preliminary Investigation

et al. 2015

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Concrete is a common material used as a shielding against ionizing radiation due to the relatively low cost and the ability to meet the structural function. State of the art in concrete shielding is that while in case of gamma radiation an increase in density by a change of aggregate is usually efficient enough, protection against neutrons is more complex. It is due to the differences in interactions of neutrons with the matter, depending on their kinetic energy and reaction cross-sections with the component atoms of the cement paste and the aggregate. Last progress in concrete evolution due to use of polymer additives (e.g. superplasticizers) together with reactive additions (e.g. silica fume) allows for a new look at the concrete design for radiation shielding purposes. One of the main advantages of concrete is its composite-type and there is a potential for the optimization of its constituents as well as mixture proportions. The paper presents the preliminary results of the project NGS-Concrete -newgeneration shielding concrete against ionizing radiation. The aim of the project is to design the composition of concrete against ionizing radiation, achieved by the use of experiment based multi-criteria optimization of materials supported by the Monte Carlo simulations. The purpose of presented studies was to evaluate neutron shielding properties of ordinary and heavy-weight magnetite concrete modified with epoxy resin and gadolinium oxide. At first the shielding efficiency against neutrons from LWR neutron flux source and Pu-Be was simulated in MCNP code. At the end the comparison of MCNP simulated results and real experiment was presented. It was proved that both methods of modification can improve neutron shielding properties concrete but gadolinium oxide is an efficient additive only for low energy neutron attenuation.

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Shielding characteristics of polymer-based concretes in neutron-radiation fields

Cited by 12 publications

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Polymers in Concrete – The Shielding against Neutron Radiation

Polymers in Concrete – The Shielding against Neutron Radiation

Numerical simulation and experimental study of PbWO ₄ /EPDM and Bi ₂ WO ₆ /EPDM for the shielding of γ -rays

NGS-Concrete - New Generation Shielding Concrete against Ionizing Radiation - the Potential Evaluation and Preliminary Investigation

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Shielding characteristics of polymer-based concretes in neutron-radiation fields

Cited by 12 publications

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Polymers in Concrete – The Shielding against Neutron Radiation

Polymers in Concrete – The Shielding against Neutron Radiation

Numerical simulation and experimental study of PbWO 4 /EPDM and Bi 2 WO 6 /EPDM for the shielding of γ -rays

NGS-Concrete - New Generation Shielding Concrete against Ionizing Radiation - the Potential Evaluation and Preliminary Investigation

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Numerical simulation and experimental study of PbWO ₄ /EPDM and Bi ₂ WO ₆ /EPDM for the shielding of γ -rays