The effect of barite proportion on neutron and gamma-ray shielding

Akkurt, I.; El-Khayatt, A.M.

doi:10.1016/j.anucene.2012.08.026

Cited by 151 publications

(54 citation statements)

References 6 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…In the same research it was proved that neutron attenuation for borated concrete in comparison to heavy concrete is of one or two orders of magnitude, but this advantage of borated concretes is removed as they have been the most activated and their activation decrease in time has been the slowest. On that background Akkurt and Elkhayat [1] stated that the most effective shielding material for mixed neutron and gamma-rays is obtained by mixed hydrogenous materials, heavy metal elements, and other neutron absorbers. In Poland, from the 60's it is assumed that the concrete containing 8-10% water (free and chemically bound) with the possible addition of boron silicate (about 70 kg/m 3 ) and thickness necessary to shield the gamma radiation from reactor will also be effective enough for neutron radiation [8].…”

Section: B-15 Frommentioning

confidence: 99%

“…Akkurt and Elkhayat [1] found that the neutron attenuation coefficients decreased linearly with the increase of barite proportion in the concrete that is in opposition to photon attenuation coefficients. They showed that attenuation coefficients of neutron and gamma-rays are linearly increased and decreased, respectively, with increasing the proportion of hydrogen and moderators in concretes.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

et al. 2015

View full text Add to dashboard Cite

Concrete has been used as a shield against high-energy photons and neutrons since the beginning of use of nuclear reaction in energy, medicine and research. From that time the progress in concrete technology is huge -very good concrete used in 60's was about 30 MPa compressive strength, and now the recommendation of ETC-C is to use in EPR nuclear power plant the concrete at least class C45/55 for airplane resistant shell or class C40/50 for other structures. The Monte Carlo computer simulations indicate that an increase in density of the shielding member has a minor effect on the weakening of neutron transport and, therefore, the optimal composition of a shielding concrete against gamma radiation is different than the optimal composition of shielding concrete against neutron radiation. Neutron stopping is a two-step effect: slowing down of fast neutrons and absorption of thermal ones. Both result from the atomic composition of the barrier. The paper presents an analysis of neutrons transport through concrete cement mortar and polymer cement composites mortar based on specially designed experiments which allows for measuring fast neutron attenuation and thermal neutron capture separately. The aim of experiments was to find an influence of the cement type, polymer addition and moisture content on both aspects of neutron shielding properties of a composite. The experimental results were confirmed in MCNP simulations. There was found an influence of cement type on fast neutron attenuation due to differences in chemical composition. Next an important improvement of both fast neutron attenuation and thermal neutron capture due to polymer modification of concrete. The last was fond of clear linear relationship between fast neutron attenuation to the hydrogen content which shows the possibility of using this phenomenon in building material investigation like measurement of moisture content or polymer content in the polymer cement composites.

show abstract

Section: B-15 Frommentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

et al. 2015

View full text Add to dashboard Cite

show abstract

“…The neutron and gamma-ray shielding properties of concrete containing different proportions of barite as an aggregate have been investigated as in (Akkurt & El-Khayatt, 2013). The macroscopic fast neutron removal crosssections have been calculated and compared with the attenuation of gamma-rays with 8 MeV photon energy, because for most shields the neutron produced at 8 MeV are most likely to penetrate.…”

Section: Introductionmentioning

confidence: 99%

Shield Modelling of Boron Neutron Capture Therapy Facility with Kartini Reactor’s Thermal Column as Neutron Source using Monte Carlo N Particle Extended Simulator

Dwiputra¹,

Harto²,

Sardjono

et al. 2016

ijpna

View full text Add to dashboard Cite

Abstract-Studies were carried out to design a shielding for BNCT facility in the end of Kartini reactor's thermal column with predesigned collimator. The design consist of selecting the material and their thickness. The shielding is required to absorb the leaking radiation until the Dose Limit Value of 20 mSv/year for radiation worker is met. The material considered were paraffin, barite concrete, borated polyethylene, stainless steel 304 and lead. The calculation was done using MCNPX tally facility with converted dose limit value of 10.42 µSv/hour. Design number two were chosen as the best from three designs which surrounded a room with length, width and height of, respectively 200 cm, 200 cm and 166.4 cm. The first and main layer are borated polyethyelene and barite concrete of 20 and 30 cm, respectively. The additional layer are borated polyethyelene and barite concrete of 15 cm and 15 cm with less volume than the main layer to decrease the primary straight radiation from the thermal column. Maximum radiation dose rate is 7.0746 µ Sv/ hour in cell 227 with average dose rate of 2.58712 µSv/hour.

show abstract

“…These can be found in Refs. [1][2][3][4][5][6][7][8][9][10][11]. In this study, we aimed to investigate both mechanical treatment and radiation shielding property of nanosized powders added cementitious materials.…”

Section: Introductionmentioning

confidence: 99%

Shielding Behaviors and Analysis of Mechanical Treatment of Cements Containing Nanosized Powders

Mutuk

Gümüş

et al. 2016

Acta Phys. Pol. A

View full text Add to dashboard Cite

In this study, we investigated linear attenuation coefficient (µ), half value layer, tenth value layer at 243, 344, 866, 1088, 1112, 1528 keV. Mechanical properties of cements containing nanosized powders (nano-SiO2, nano-Fe2O3, nano-Al2O3) are obtained. According to compressive strength results nano-SiO2 added cementitious material gave the highest strength. Moreover, all the nanopowders added samples showed higher compressive strength with respect to reference sample. The experimental linear mass attenuation coefficients µ, half value layer, tenth value layer for cementitious material were compared with theoretical values obtained using XCOM. The experimental results were found to be in good agreement with the theoretical values.

show abstract

The effect of barite proportion on neutron and gamma-ray shielding

Cited by 151 publications

References 6 publications

Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

Experiments on Neutron Transport through Concrete Member and the Potential for the Use in Material Investigation

Shield Modelling of Boron Neutron Capture Therapy Facility with Kartini Reactor’s Thermal Column as Neutron Source using Monte Carlo N Particle Extended Simulator

Shielding Behaviors and Analysis of Mechanical Treatment of Cements Containing Nanosized Powders

Contact Info

Product

Resources

About