Full-text resources of PSJD and other databases are now available in the new Library of Science.
Visit https://bibliotekanauki.pl
Preferences help
Polish version English version Language
enabled [disable] Abstract
Number of results

Results found: 20

Number of results on page
first rewind previous Page / 1 next fast forward last

Search results

Search:
in the keywords:  25.20.Dc
help Sort By:

help Limit search:
first rewind previous Page / 1 next fast forward last
1
Content available remote

Investigation of Gamma Ray and Neutron Attenuation Coefficients for Granites Produced in Turkey

100%
Ozyurt O., Altinsoy N., Buyuk B.
Acta Physica Polonica A
|
2015
|
vol. 127
|
issue 4
1268-1270
EN
In this study, shielding properties of granites which are produced in Turkey were studied for gamma ray and neutrons. Linear and mass attenuation coefficients for gamma ray were measured at 1.17 MeV, 1.33 MeV and 0.662 MeV by gamma spectrometry system containing NaI(Tl) detector. Pu-Be source was used in measuring linear neutron attenuation coefficients of the granite samples. Measurements were carried out by using narrow beam geometry by using gamma and neutron transmission technique. The gamma transmission results have been compared with winXCOM calculations and a good correspondence has been obtained.
2
Content available remote

Wall Thickness Measurement of Pipes by Using Digital Radiography

100%
Cobanoglu M., Altinsoy N.
Acta Physica Polonica A
|
2015
|
vol. 127
|
issue 4
1261-1263
EN
One of the most important parameters in a pipeline to be monitored and measured is the wall thickness. Pipe wall thickness can vary after a certain period of time, as a result of accumulation of various chemical or physical effects. Pipe wall thickness can be monitored by the proper use of ultrasonic or radiographic inspection methods even while the plant is in operation. Only the radiographic method assures inspection without costly removal of insulation material during operation of the plant. The purpose of this study is to define the wall thickness of pipes by using digital radiography technique. The outer diameter of the studied pipes is ranging from 51 mm to 60.3 mm and wall thickness is ranging from 2.9 mm to 3.6 mm. Experiments were repeated by changing the "focal detector distance" and "pulse" parameters.
3
Content available remote

Gamma Attenuation Properties of Some Aluminum Alloys

100%
Yıldırım S., Tugrul A., Buyuk B., Demir E.
Acta Physica Polonica A
|
2016
|
vol. 129
|
issue 4
813-815
EN
In the present work, several commonly used aluminum alloys were investigated for their protective properties against gamma radiation. The gamma transmission technique was used to study the gamma attenuation behavior of the alloys. Cs-137 (0.662 MeV) and Co-60 (1.25 MeV) gamma radioisotope sources, which have relatively medium and high gamma energy levels, were used as gamma sources. The linear and mass attenuation coefficients of the aluminum alloys were measured. The mass attenuation coefficients of the samples were compared with the theoretical values which were calculated using XCOM computer code. The difference between the experimental and theoretical values was below 5%. In addition half-value layer (HVL) values for the studied aluminum alloys were calculated using the linear attenuation coefficients. The attenuation coefficients of the different aluminum alloys were compared. The biggest HVL was observed for 1050 alloy, for both gamma isotope sources, which means the smallest gamma attenuation capability among the studied alloys. It is concluded that the alloys were applicable for the gamma radiation shielding applications.
4
Content available remote

Radiation Shielding Effect of Boron Carbide Aluminum Metal Matrix Composite

100%
Akkaş A., Tugrul A., Addemir O., Marşoğlu M., Ağacan B., Büyük B.
Acta Physica Polonica A
|
2015
|
vol. 127
|
issue 4
947-949
EN
Boralyn (Al/B₄C) composite material is produced chiefly of boron carbide and aluminum. Boron Carbide is an important material for the nuclear industry due to high neutron absorption cross-section. This composite is used as shielding materials to absorb neutrons in the nuclear reactors and control road materials. In this study we investigated Al/B₄C composites against gamma radiation. For that purpose, 5 wt.%, 10 wt.%, 15 wt.% and 20 wt.% reinforcement content were investigated. Cs-137 gamma radioisotope source which has 662 keV gamma energy photons were used. For each material, linear and mass attenuation coefficients were calculated. Theoretical mass attenuation coefficients were calculated from XCOM computer code. The theoretical results were compared with experimental results. The results were showed that increasing the amount of Boron Carbide compound content of boralyn composite material decrease the linear and mass attenuation coefficient of materials
5
Content available remote

Shielding Effect of Boron Carbide Aluminium Metal Matrix Composite against Gamma and Neutron Radiation

100%
Akkas A., Tugrul A., Buyuk B., Addemir A., Marsoglu M., Agacan B.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-176-B-179
EN
In this study, boralyn (boron carbide-aluminum metal matrix composite material - Al/B₄C) composite materials were investigated on shielding effect against gamma and neutron radiations. The samples were prepared as 5 wt%, 10 wt%, 15 wt%, and 20 wt% reinforcement content and for each content of material has composed in five different average particle sized (3 μm, 53 μm, 113 μm, 200 μm, and 500 μm). Linear and mass attenuation coefficients were calculated experimentally for each composite material against Cs-137 gamma source. Theoretical mass attenuation coefficients of material were calculated by using XCOM computer code. Then the theoretical results were compared with experimental results. Then, macroscopic cross-section values were calculated experimentally for each composite material against Pu-Be neutron source. As the conclusion of the study, it could be understood that in spite of decrease of the attenuation coefficient against gamma radiation, the adding materials give rise to increase the shielding ability of material against neutron radiation.
6
Content available remote

Gamma Attenuation Behavior of Some Stainless and Boron Steels

100%
Buyuk B.
Acta Physica Polonica A
|
2015
|
vol. 127
|
issue 4
1342-1345
EN
In the present work gamma attenuation behavior of some commonly used commercial stainless steels and boron steels were investigated. 303, 304, 310, 316, 430 stainless steels and ZF7B, 27M12C5B, 30MNB5 boron steels were studied against Cs-137 and Co-60 gamma radioisotopes. The linear and mass attenuation coefficients of the samples were measured by using gamma transmission technique. Mass attenuation coefficients were compared with the theoretical values which were calculated by using XCOM computer code. Theoretical and experimental mass attenuations were closed to each other. In addition half-value thickness (HVT) values of the samples were calculated and compared with the results of lead (Pb). European Union has published the directive in 2002 and recast in 2011 about Restriction of Some Hazardous Substances (RoHS) which included Pb. This study shows that 303, 304, 310 and 316 stainless steels and ZF7B, 27M12C5B, 30MNB5 boron steels are some of the candidate materials for using in gamma shielding applications instead of lead.
7
Content available remote

Gamma Attenuation Behavior of h-BN and h-BN-TiB_2 Composites

100%
Buyuk B., Beril Tugrul A., Okan Addemir A., Ay N.
|
|
vol. 125
|
issue 2
420-422
EN
Hexagonal boron nitride (h-BN) and hexagonal boron nitride-titanium diboride (h-BN-TiB_2) composites are advanced materials for high-tech applications. They were investigated against gamma radioisotope sources Cs-137 and Co-60 which have gamma peaks 0.662 MeV for Cs-137, and 1.17 and 1.33 MeV for Co-60. Materials have been produced at 1800C temperature in argon atmosphere without pressure during 2 h time. Linear and mass attenuation coefficients were calculated for the materials. Gamma transmission technique was used in the experiments. The experimental investigated mass attenuation coefficients of the materials for Cs-137 and Co-60 gamma radioisotope sources were compared with XCOM computer code. For h-BN-TiB_2 composites the ratio of TiB_2 in the composites is 55% by weight. So gamma attenuation effects of adding TiB_2 to h-BN were discussed. It could be said that adding TiB_2 to h-BN increases the linear gamma attenuation of the samples.
8
Content available remote

Comparison of Lead and WC-Co Materials against Gamma Irradiation

100%
Buyuk B., Tugrul A.
|
|
vol. 125
|
issue 2
423-425
EN
According to RoHS (Restriction of Hazardous Substances) directive of European Union it is restricted using lead in many equipment and applications. It is possible to enlarge the restriction of lead usage in some other applications which is including some of nuclear applications in the future. Therefore new materials or systems need to be developed instead of lead as radiation shielding materials and/or collimators. In this study pure tungsten, tungsten carbide-cobalt (WC-Co) materials were investigated against gamma radiation. For gamma radiation Cs-137 and Co-60 gamma radioisotope sources were used. The linear and mass attenuations were calculated. The experimental results were compared with XCOM computer code. Usage possibilities of WC-Co instead of lead in nuclear applications as gamma shielding material were discussed. It has been investigated that the linear gamma attenuation coefficients of lead and WC-Co are very close to each other. Therefore it could be said that WC-Co materials is an alternative promising material which could be used instead of lead as gamma shielding material and/or collimator.
9
Content available remote

Evaluation of Gamma Penetration through Plain Carbon Steels

100%
Durmaz H., Beril Tugrul A., Buyuk B.
|
|
vol. 125
|
issue 2
469-472
EN
In this study, 1010, 1040, 1050 and 1090 carbonized steels were investigated against gamma radioisotope sources on their gamma attenuation properties. Co-60, Cs-137 and Ir-192 gamma radioisotopes which are commonly used in industrial applications were used in the experiments. Half-value layers were carried out for studied carbonized steels against all studied gamma radioisotopes. In addition, the linear and mass attenuation coefficients were determined for each carbonized steels at different gamma radioisotope sources. The theoretical mass attenuation coefficients were calculated from XCOM computer code for all samples at specific energies of Co-60, Cs-137 and Ir-192 gamma sources. The theoretical and experimental results were compared with each other.
10
Content available remote

Investigation on the Effects of Boron Carbide Particle Size on Radiation Shielding Properties of Boron Carbide-Titanium Diboride Composites

100%
Buyuk B., Tugrul A., Aktop S., Addemir A.
Acta Physica Polonica A
|
2013
|
vol. 123
|
issue 2
177-179
EN
Boron carbide is a material which has wide application areas in industry including nuclear technology. Titanium diboride-boron carbide composites which were produced from different boron carbide particle sizes were studied for searching of the behaviour against the gamma ray. Micron size and submicron size boron carbide were used to produce composite materials. The volume of boron carbide and titanium diboride in the composites are 85% and 15%, respectively. For the investigation of the gamma radiation behaviour of these materials, Cs-137 radioisotope was used as gamma source in the experiments which has a single gamma-peak at 0.662 MeV. Gamma transmission technique was used for the measurements. The effects of boron carbide particle size on radiation attenuation of titanium diboride-boron carbide composites were evaluated in relation with gamma transmission and the results of the experiments were interpreted and compared with each other. It could be understood that decrease of particle size of boron carbide in boron carbide-titanium diboride composites causes higher linear and mass attenuation coefficient values. So, submicron size boron carbide used composite materials are more convenient than micron size boron carbide used composite materials as radiation shielding materials for nuclear applications.
11
Content available remote

Investigation of Behaviour of Titanium Diboride Reinforced Boron Carbide-Silicon Carbide Composites against Cs-137 Gamma Radioisotope Source by Using Gamma Transmission Technique

100%
Buyuk B., Tugrul A., Akarsu A., Addemir A.
|
EN
Boron carbide is a material which has wide application areas in industry including nuclear technology. Titanium diboride reinforced boron carbide-silicon carbide composites were studied for searching of the behaviour against the gamma ray. It has been adopted that depending on their properties such improved materials can be used in nuclear technology. For the investigation of the gamma radiation behaviour of these materials, Cs-137 radioisotope was used as gamma source in the experiments which have a single gamma-peak at 0.662 MeV. Gamma transmission technique was used for the measurements. Different reinforcing ratios, titanium diboride reinforced boron carbide-silicon carbide composites were evaluated in relation to gamma transmission and the results of the experiments were interpreted and compared with each other. It could be understood that the increasing ratio of titanium diboride in boron carbide-silicon carbide composites causes higher hardness, strength and linear attenuation coefficient values but decrease the mass attenuation coefficient.
12
Content available remote

Investigation for Remediation of Selenium Aqueous Environment with Using Organic Pillared Bentonite by Radiotracer Technique

100%
Tugrul A., Haciyakupoglu S., Erenturk S., Karatepe N., Baytas F., Baydogan N., Altinsoy N., Buyuk B., Orucoglu E., Demir E., Camtakan Z., Okka M.
Acta Physica Polonica A
|
2015
|
vol. 127
|
issue 4
1186-1188
EN
In this study remediation of selenium ions from aqueous solutions was investigated using organic pillared bentonite as an adsorbent. Organic pillared bentonite was produced from Resadiye (Tokat, Turkey) bentonite using hexadecylpyridinium chloride and aluminum polyoxy-cations. All the experiments were carried out by tracing with selenium radioisotope. For the production of the radioactive selenium radioisotope, selenium dioxide was irradiated in the central thimble of ITU TRIGA Mark II Training and Research Reactor at Energy Institute of Istanbul Technical University. Radioactivity measurements carried out by the gamma-ray spectroscopy system were used to determine of selenium isotope. The relative importance of test parameters like concentration of adsorbate, pH of the solution and contact time on adsorption performance of organic pillared bentonite for selenium ion was studied. Evaluation of experiments for different parameters showed possibility of remediation of selenium from aqueous media by using organic pillared bentonite.
13
Content available remote

Comparison of Radiation Properties of Tungsten and Additive Metal Coatings on 321 Stainless Steel Substrate

63%
Demir E., Karabas M., Sonmez S., Tugrul A., Ovecoglu M., Buyuk B.
Acta Physica Polonica A
|
2017
|
vol. 131
|
issue 1
71-73
EN
In the present work, the gamma and neutron attenuation behaviors of tungsten, tungsten copper, and tungsten boron-carbide coatings on 321 stainless steel substrate were investigated against Cs-137 and Co-60 gamma radioisotopes and Pu-Be neutron source. The experimental results were compared and evaluated with pure 321 stainless steel to obtain gamma and neutron shielding properties of the coating materials. Tungsten, tungsten copper, and tungsten boron-carbide coatings on 321 stainless steel substrate were fabricated by atmospheric plasma spraying technique. Gamma and neutron transmission technique were used in this study to investigate the radiation behaviors of the coated materials. Linear attenuation coefficients of coated samples were carried out for Pu-Be neutron source. Transmittance values for each specimen were calculated at 0.662 MeV and 1.25 MeV gamma energies. The experimental results were evaluated for radiation shielding properties of the coated samples against gamma and neutron source with pure 321 stainless steel.
14
Content available remote

Processing, Mechanical and Nuclear Characterization of Boron Carbide Ceramics Consolidated by Spark Plasma Sintering

63%
Cengiz M., Ozer S., Buyuk B., Tugrul A., Yucel O., Goller G., Sahin F.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-187-B-189
EN
Boron carbide (B₄C) ceramics were produced by spark plasma sintering technique with 5, 10, 15, and 20 vol.% aluminum (Al) in order to improve sintering behaviours of B₄C ceramics. B₄C ceramics were produced, having square cross-section and 50 × 50 × 5 mm³ dimensions. The sintering process was carried out at different temperatures by applying 40 MPa of pressure with 100°C/min under vacuum. The effects of various amounts of Al additive and sintering temperature on density, vickers hardness, fracture toughness and microstructure were examined. The hardness and fracture toughness of the samples were evaluated by the Vickers indentation technique. Microstructures of the samples were characterized by scanning electron microscopy technique. Fast neutron attenuation properties of the ceramics having highest density were also investigated.
15
Content available remote

Radiation Shielding Properties of Spark Plasma Sintered Boron Carbide-Aluminium Composites

63%
Buyuk B., Tugrul A., Cengiz M., Yucel O., Goller G., Sahin F.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-132-B-134
EN
In this study gamma and neutron attenuation properties of boron carbide-aluminium (B₄C-Al) composites were investigated. B₄C-Al composites were produced by spark plasma sintering method. Aluminum percentages in the B₄C-Al composites were 0%, 10%, 15%, and 20% by volume. The composite materials were performed against gamma and neutron sources. Cs-137 and Co-60 gamma radioisotopes were used as gamma sources and Pu-Be neutron howitzer was used for neutron source. Theoretical mass attenuation coefficients were determined by using XCOM computer code and compared with the experimental results. It has been seen that the experimental results were close to the theoretical results. Total macroscopic cross-sections of the samples were determined for Pu-Be neutrons. It is concluded that increasing aluminum ratio in the B₄C-Al composites causes higher gamma attenuation behavior for Cs-137 and Co-60 gamma sources and the total macroscopic cross-sections of the B₄C-Al composites decrease by increasing Al concentration.
16
Content available remote

An Investigation on the Mass Attenuation Coefficients of W-VC-C and W-VC-TiC-C Composites for Gamma Radioisotopes

63%
Tuğrul A., Demir E., Yılmaz O., Sönmez S., Öveçoğlu M., Büyük B.
Acta Physica Polonica A
|
2016
|
vol. 129
|
issue 4
724-727
EN
In this study, tungsten-vanadium carbide-graphite and tungsten-vanadium carbide-titanium carbide-graphite composites (W-VC-TiC-C) which can be used in high-tech equipment were investigated against different gamma radioisotopes. The composite materials were produced via mechanical alloying method in two groups; one of them includes 93% tungsten (W), 6% vanadium carbide (VC) and 1% graphite (C) which was synthesized during three different alloying times (6, 12, 24 hours). Other group of the samples were composited as 91% tungsten, 6% vanadium carbide (VC), 2% titanium carbide (TiC) and 1% graphite (C) which has also three different alloying times (6, 12, 24 hours). Gamma transmission technique was used in the experiments to investigate the gamma attenuation properties of the composite materials. Linear and mass attenuation coefficients of the samples were determined in the experiments and theoretical mass attenuation coefficients were calculated using widely acknowledged XCOM computer code. The experimental mass attenuation coefficients and calculated theoretical results were compared and evaluated with each other. Results showed that gamma attenuation coefficients of the composite materials dependent on alloying time. It can be concluded that increasing the tungsten ratio causes higher linear attenuation coefficient which decreases with increasing gamma energies.
17
Content available remote

The Effect of Pumice Rate on the Gamma Absorption Parameters of Concrete

63%
Akkurt I., Akyildirim H., Mavı B., Kilinçarslan Ş., Başyığıt C.
Acta Physica Polonica A
|
2012
|
vol. 121
|
issue 1
144-146
EN
Since the technology concerning gamma radiation showed a rapid development, it became a necessity to be protected from it. One of the common shielding materials for this purpose is concrete. This study aims to give the effect of pumice rate on the gamma radiation attenuation coefficients of normal concrete (ρ = 2.476 g cm^{-3}) containing different rates of pumice mineral. Pumice, for which the Gölcük region in Isparta province is rich, is a volcanic originated spongy and porous mineral. Although it is a light material, it has a high comprehensive strength and heat resistance. So it became a common construction material in buildings. In the study, the variation of attenuation coefficients for concretes of different pumice rates were measured for 662, 1173 and 1332 keV photons using a NaI(Tl) detector. The experimental values were compared with the theoretical ones obtained by XCOM code.
18
Content available remote

Determination of Radiation Shielding Properties of Some Polymer and Plastic Materials against Gamma-Rays

51%
Gurler O., Akar Tarim U.
|
EN
A Monte Carlo code is proposed for determination of mass attenuation coefficients of gamma rays for some polymer and plastic materials. It is based on simulation of interaction processes of gamma rays with the energy of 59.5, 80.9, 140.5, 279, 356.5, 511, 661.6, 1173.2, 1332.5 keV with matter. The method was tested by comparison of the simulation results with the literature values (ANSI/ANS-6.4.3 and GRIC toolkit). The compatible behaviour of mass attenuation coefficients versus incident photon energy for the investigated energy range approves the use of this code for the extended energy range and several materials. Also, the values of half-value layer were calculated for assessment of shielding effectiveness of these materials.
19
Content available remote

Evaluation of Multiple Backscattering and Saturation Thickness of Gamma Rays

51%
Akar Tarim U.
|
EN
A Monte Carlo code was written to determine the saturation thickness for multiply scattered gamma rays from aluminium targets. Interactions of incident gamma rays with the energies of 123, 279, 360, 511, 662, 1115, and 1250 keV were simulated. This work aims to design a convenient code which can be used in investigations on gamma backscattering. Obtained results for saturation thickness values have been compared with experimental ones and the Monte Carlo N-particle (MCNP) code results, and showed good agreement. Also, based on the similar behavior of number of multiple scattered photons between these three methods, the expected spectrum of singly or multiply scattered photons which is not possible to observe with experiment has been presented.
20
Content available remote

Monte Carlo Calculations for Photon Attenuation Studies on Different Solid Phantom Materials

45%
Gundogdu O., Tarim U., Gurler O.
Acta Physica Polonica A
|
2017
|
vol. 132
|
issue 3
1032-1035
EN
The linear attenuation coefficients of water and some solid phantom materials, namely of solid water RMI-457, of plastic water, of RW3 solid water, and of Perspex were determined by Monte Carlo calculations, for gamma-ray photons with energies of 59.5, 80.9, 140.5, 356.5, 661.6, 1173.2, and 1332.5 keV. The calculated values were compared with the experimental results presented by other researchers and with theoretical values obtained using the XCOM database. Good agreement was observed between the calculations, the experimental, and the theoretical values. The results indicate that the process in Monte Carlo code can be followed to determine the equivalency of other materials at several energies. Three shielding factors such as half-value layer, tenth-value layer, and mean free path were calculated at all considered gamma-ray energies.
first rewind previous Page / 1 next fast forward last
JavaScript is turned off in your web browser. Turn it on to take full advantage of this site, then refresh the page.