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1
Content available remote

Investigation of Radon Concentrations in Pamukkale-Turkey

100%
Kulalı F., Akkurt İ.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-445-B-446
EN
Radon is an inert gas produced by the radioactive decay of radium with a half-life of 3.81 days. Radon is the largest source of natural ionizing radiation and every 2.6 km² of surface soil, to a depth of 15 cm, contains approximately 1 gram of radium, which releases radon in small amounts to the atmosphere. On a global scale, it is estimated that 91 TBq of radon are released from soil annually. In this work, the radon concentration in soil gas, which is transported from soil (1 m depth), is measured at five points in Pamukkale and its neighbourhood.
2
Content available remote

Determination of Radiation Shielding of Concrete Produced from Portland Cement with Boron Additives

81%
Davraz M., Pehlıvanoğlu H., Kilinçarslan Ş., Akkurt İ.
Acta Physica Polonica A
|
2017
|
vol. 132
|
issue 3
702-704
EN
Concrete is a material which is widely used for neutron shielding in such building constructions as nuclear power stations, particle accelerators and medical hospitals. Concrete is very significant for neutron shielding, because is contains some elements which help to moderate very penetrative fast neutrons. Boron increases the neutron shielding effectiveness of concretes. Boron can be added to concrete in different ways, by addition of boron to the water, used in concrete, or by addition of boron containing natural minerals. In this study, three samples of concrete were produced using B₂O₃ additives material, boron-modified active belite and Portland cement. Neutron absorption coefficients of the produced three different types of concrete samples were obtained through experiments. It is concluded that the addition of boron to concrete is an alternative option to be used for the purposes of neutron shielding.
3
Content available remote

Radioactivity Measurement on Dental Resin Composites

81%
Akkurt İ., Ermiş R., Baş P., Günoğlu K.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-34-B-36
EN
Radioactivity is mainly due to natural ones from earth and also from outside of the atmosphere so-called cosmic radiation. Although radiation sources and their dose effect on humans are known, there is still some conflict on their health effect especially on dental restoration. The limited data for radioactive dental materials and their potential risks for patient makes those materials interesting to be investigated. For this purposes, uranium, thorium and potassium activity have been measured in some dental restorative materials, such as resin composites containing silica and zirconia particles as filler loading, using gamma spectrometer system with NaI(Tl) detector.
4
Content available remote

Calculation of Gamma Strength Functions for Photonucleon Reactions

81%
Karpuz N., Mavi B., Akkurt İ.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-414-B-416
EN
The cross section for (γ,N) reaction is important for investigation of nuclear structure, especially in low-energy giant dipole resonance (GDR). The total cross sections of ^{12}C(γ,n)^{11}C and ^{12}C(γ,p)^{11}B reactions, calculated using TALYS 1.2 nuclear code, are 15.5 to 40 MeV and 15 to 110 MeV, respectively. In the calculations, the default pre-equilibrium models and Brink-Axel Lorentzian model in all of the gamma strength functions have been used. The effects of the gamma strength function on the cross section exchange data has determined the most compatible model type. The results are compared with the experimental data from the EXFOR database and the evaluated nuclear data from TENDL-2012. Our calculated results are in good agreement with the previously reported experimental results.
5
Content available remote

Variation of Energy Resolution with Distance for a NaI(Tl) Detector

81%
Akkurt İ., Arda S., Gunoglu K.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-422-B-423
EN
As the nuclear radiation has started to be used in a variety of different fields, it is important to be protected from it, and thus the radiation measurement becomes vital. The quality of the performance of a detection system, used for the energy measurements, is important. It is characterized by the width of the pulse-height distribution, obtained for the particles of the same energy (monoenergetic source). The energy spectrum of a radiation source depends on the type and energy of the incident particle and the type of the detector. In this work the energy resolution of a 3"×3" NaI(Tl) detector has been measured for photon energies of 511, 662, 835, 1173, 1275, and 1332 keV, and its variation with the detector-source distance was investigated. The energy resolution of a detector system is obtained from the peak full width at one-half of the maximum height (FWHM) of a single peak (for a particular energy) as a function of detector-source distance. It was found that the energy resolution has decreased with the increasing distance.
6
Content available remote

Determination of Natural Radioactivity and Associated Radiological Hazard in Excavation Field in Turkey (Oluz Höyük)

81%
Çetin B., Öner F., Akkurt İ.
Acta Physica Polonica A
|
2016
|
vol. 130
|
issue 1
475-478
EN
The level of natural radioactivity may be varied with the increase in dependence of the depth into the earth. In present study, soil samples from different depths were collected in Oluz Höyük excavation area. The radionuclide concentrations in soil samples were determined by gamma-ray spectrometer which contains 3" × 3" NaI(Tl) detector connected to multichannel analyser. The photopeaks at 1460, 1764, and 2615 keV due to ⁴⁰K, ²²⁶Ra and ²³²Th, respectively, have been used. The obtained activity concentrations of ⁴⁰K, ²²⁶Ra and ²³²Th ranged from 656.03 to 1791.85 Bq/kg, 62.39 to 180.93 Bq/kg and 48.31 to 125.43 Bq/kg, respectively. To assess the radiological hazard of the natural radionuclides content in the soil samples of these area, the radium equivalent activities (the minimum value was 181.99 Bq/kg and the maximum value was 497.97 Bq/kg), the absorbed dose rate (the minimum value was 86.83 nGy/h and the maximum value was 237.22 nGy/h), annual effective dose rate (the minimum value was 0.11 mSv/y and the maximum value was 0.29 mSv/y) and external hazard index (the minimum value was 0.49 and the maximum value was 1.35) were calculated using measured activities.
7
Content available remote

Excitation Functions of (d,n) Reactions on Some Light Nuclei

81%
Noori S., Karpuz N., Akkurt İ.
Acta Physica Polonica A
|
2016
|
vol. 130
|
issue 1
484-486
EN
Nuclear reactions of the induced deuteron particles with light nuclei have been investigated in the history of nuclear physics. In this study, excitation functions for the deuteron reactions ⁶Li(d,n)⁷Be, ¹²C(d,n)¹³N, ¹⁶O(d,n)¹⁷F have been calculated by using Monte Carlo nuclear reaction simulation code TALYS 1.6, considering equilibrium and pre-equilibrium effects. The calculated theoretical (d,n) excitation functions are compared to the experimental reaction cross-sections in the literature.
8
Content available remote

Investigation of Buildup Factor in Gamma-Ray Measurement

81%
Akyildirim H., Waheed F., Günoğlu K., Akkurt İ.
Acta Physica Polonica A
|
2017
|
vol. 132
|
issue 3
1203-1206
EN
Gamma ray measurement is an important issue in nuclear technology, since it is widely used in industry, medicine, agriculture, education research, and some military applications. Gamma ray is also needed to build radiation protection, which is very useful for human health. When gamma radiation penetrates through shielding material, it generates two radiation components within or beyond the shield, namely: the uncollided and the collided photons. Therefore, the buildup factor is an important parameter for gamma ray measurement. Buildup factor is defined as the ratio of the total number of particles at a given point to the number of uncollided particles, at that same point. In this work, we evaluate the gamma-ray buildup factors for copper (Cu-29), as a function of energy, for 0.511, 0.662, 1.275 MeV, by using cesium and sodium radioactive sources. The results show that the value of energy buildup factor decreases with increasing gamma energy, and increases with increasing thickness. Moreover, it was found that at high energies (1.275 MeV), the absorption buildup factor is at minimum when the energy is at high level. The results also reveal that there is no contribution from the scattering photons to the value of buildup factor, in general, at low intensity levels, when the geometry structure is built well. While for bad geometry, the detector measures intensity, which is greater than that described by the main linear attenuation coefficient, because the scattered photons will be detected as well. All in all, in order to get rational results, a well geometry should be used for the future applications.
9
Content available remote

Determination of Natural Radioactivity from ^{232}Th with Gamma-Ray Spectrometer in Dereköy-Yazır (Southwestern Anatolia)

81%
Uyanik N., Öncü Z., Uyanik O., Akkurt İ.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-441-B-442
EN
This study presents new data on the baseline concentrations of Thorium over the Dereköy-Yazır (Ağlasun-Burdur) volcanic area. Portable gamma-ray spectrometer was used for natural thorium mapping. In situ measurements were made in the field, in the area of 7.5 km² at 165 points. Variations in the Th concentration in the surficial environment of the Dereköy-Yazır region appear to be related to bedrock lithology. The measured thorium concentration varies between 0.68-36 ppm, in the studied area. The highest concentration values were obtained from volcanic rocks. The outcropping volcanic rocks in the region are Pliocene alkaline basalts.
10
Content available remote

Investigation of Double Differential Cross Sections of (γ,p) Reaction for ¹²C Nuclei

81%
Karpuz N., Mavı B., Akkurt İ.
Acta Physica Polonica A
|
2016
|
vol. 130
|
issue 1
313-315
EN
Photonuclear reaction data, is important for basic and applied research. In additional to this, double differential data is especially vital in the field of nuclear medicine. The increase in the number of patients, admitted for treatment of cancer with heavy ions, poses a serious problem in terms of the risk of secondary cancer, as a result of exposure to particles of different energy and angle values, released after the nuclear reaction. The main point here is the possibility of damaging organs other than the treated one by the radiation generated in the reactions during the heavy ion therapy. Based on this, in order to assess the risk of secondary cancer the investigations of the double differential cross sections of reaction are required. Double differential cross sections of (γ,p) photonuclear reaction for ¹²C nuclei were calculated as functions of incoming photon energy and angle. Nuclear reaction simulation program TALYS 1.2 was used in the calculations. The calculated cross sections were compared with both the experimental cross sections and the evaluated cross sections available in literature.
11
Content available remote

The Measurement of Gamma Dose in Radiotherapy Unit

81%
Akkurt İ., Kara Ü., Yildiz M., Kaya V.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-367-B-369
EN
Cancer is one of the most deadly diseases posing threat for our health. The most important method for eradicating of cancer cells is photoradiotherapy. Electrons accelerated by the accelerator are converted to photons in the process of bremsstrahlung. These photons are focused on diseased cells. Photon leaving accelerator head should assure a given dose intensity in cancer cells. Measuring of beam parameters at apparatus output is essential to determine the dose. In this study, Suleyman Demirel University research and education hospital in radiation Oncology department which has located at 18 MeV accelerator in energy gamma dose was measured.
12
Content available remote

Determination of ⁴⁰K Concentration in Gravel Samples from Konyaalt i Beach, Antalya

81%
Seçkiner S., Akkurt İ., Günoğlu K.
Acta Physica Polonica A
|
2017
|
vol. 132
|
issue 3
1095-1097
EN
Terrestrial radioactivity is caused by the radioactive elements, located in various amounts in soil and rocks. The concentration of radioactive elements varies with the geographical and geological structure of the region and with the mineralogical composition of soil and rock. In this study, ⁴⁰K activity concentrations in gravel samples, collected from Konyaaltı Beach, were measured. The measurement was performed using gamma ray spectrometery at gamma spectrometry laboratory of Süleyman Demirel University.
13
Content available remote

Adult Patient Radiation Doses with Multislice Computed Tomography Exam: MSCT Standard Protocols

81%
Kara U., Kaya A., Tekin H., Akkurt İ.
Acta Physica Polonica A
|
2017
|
vol. 132
|
issue 3
1126-1127
EN
Radiation is energy, and it is widely used in a variety of fields, especially in industry and medical science. In hospital, ionizing radiation like X-ray is an extensive exam that has been used to help physicians to have a view into the body, without having to make a medical application. Computed tomography scan uses ionizing radiation, and it is a nearly perfect diagnostic unit that allows the physician to see the picture of the human body. Computed tomography scan technology has progressed over the years, and it is an increasingly powerful and effective unit in the diagnostic radiology. Exposure to ionizing radiation is known to increase the risk of cancer. The aim of this study was to assess the radiation exposure received during computed tomography in a sample representative of the current state of practice in adult patients.
14
Content available remote

Angular Distribution of Bremsstrahlung Photons in Ta Target for 40 MeV Electron Beam

81%
Demir N., Kuluöztürk Z., Akkurt İ.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-443-B-444
EN
Bremsstrahlung photons are created by electron beams de-accelerating in electric field (coupling with a thin radiator) and are used in a variety of different fields. In nuclear physics experiments it is important to transport and focus the created photon beam into the experimental cavity. Here angular distribution of the photon beam is one of the important parameters, which should be known. In this study a FLUKA simulation has been done to obtain angular distribution of photon beam created by interaction of 40 MeV electron beam with the tantalum (Ta) radiator of varied thickness, which is planned to be used in bremsstrahlung photon facility at TARLA (Turkish Accelerator and Radiation Laboratory in Ankara). TARLA will be the first facility of Turkish Accelerator Center project.
15
Content available remote

Calculation of Detection Efficiency for the Gamma Detector using MCNPX

81%
Akkurt İ., Tekin H., Mesbahi A.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-332-B-334
EN
Radiation detection has been a main interest for researchers as all kind of produced particles in atomic and subatomic physics based on the measurement systems so-called detector. Detection efficiency is one of the main parameter in detection system besides many other different parameters of the detector. The absolute efficiency of the gamma detector system will be used at Turkish Accelerator and Radiation Laboratory at Ankara (TARLA) is simulated using MCNPX code (version 2.4.0). The MCNP is the general purpose MC code that can be used for neutron, photon, electron or coupled neutron, photon, electron transport. The results have been obtained for NaI(Tl) detector system and compared with the experimental results. A good agreement was found between calculation and experiment.
16
Content available remote

Performance of Boron-Carbide as Radiation Shielding

81%
Kara Ü., Tekin H., Calik A., Akkurt İ.
Acta Physica Polonica A
|
2015
|
vol. 128
|
issue 2B
B-335-B-336
EN
Radiation is widely used many fields, especially in medical science. The shielding is the basic method of protection against unnecessary influence of radiation. One of the tools most commonly used in nuclear medicine is vial pig container. Usually lead is used as shielding material in vial pigs to cover radiation source, such as Tc^{99m} which is the most widely used radiopharmaceutical in nuclear medicine. In this study boron carbide has been tested as an substitute of lead in vial pig. The measurement has been performed with the Geiger-Müller counter and the personal combined radiation detectors.
17
Content available remote

Calculations of Temperature Rise in Al, Cu and Fe Photon Collimators for 8-32~MeV Photon Beams

81%
Kuluöztürk Z., Demır N., Akkurt İ.
Acta Physica Polonica A
|
2017
|
vol. 132
|
issue 3
1168-1170
EN
We have focused on temperature changes in the collimator at the TARLA bremsstrahlung photon facility. One of the important parameters during the design of an ideal collimator, especially for high-energy photons, is temperature rise in the collimator material. For this purpose, energy deposition in the collimator materials was simulated using the FLUKA Monte Carlo code. Depending on energy deposition values, temperature rise in the collimator materials of Al, Cu and Fe was calculated for photon beams with 8-32 MeV energies.
18
Content available remote

Determination of Radiation Attenuation Coefficients of Concretes in Different Densities

81%
Akkurt İ., Günoğlu K., Başyiğit C., Akkaş A.
Acta Physica Polonica A
|
2013
|
vol. 123
|
issue 2
374-375
EN
The density of the concrete is important parameter for different properties. Using different types and rates of aggregates cause different densities of the concretes. Radiation shielding properties can be varied with the density and it is important to obtain optimum density for this purpose. In this study radiation attenuation coefficients were measured by comparison of five different densities of concrete that called lightweight, semi-lightweight, ordinary and semi-heavyweight and heavyweight. For this purpose concretes were produced with suitable aggregate in laboratory conditions and determined some physical and mechanical properties. The total linear attenuation coefficient measurements have been obtained by a collimated beam of gamma ray from sources ^{60}Co.
19
Content available remote

Calculations of Double Differential Cross Sections on ⁵⁶Fe, ⁶³Cu and ⁹⁰Zr Neutron Emission in Proton Induced Reactions

81%
Karpuz Demır N., Çetın B., Akkurt İ., Noori S.
Acta Physica Polonica A
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2017
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vol. 132
|
issue 3
1181-1185
EN
In general, the deep understanding of proton-induced reactions is a crucial step for the further development of nuclear reactions theory. However there has been an interesting focus in nuclear physics. Some applications require accurate nuclear reaction data of common cross sections and especially need the data of neutron and proton induced energy-angle correlated spectra of secondary particles, as well as double differential cross sections. Double-differential nucleon-production cross-sections of ⁵⁶Fe, ⁶³Cu and ⁹⁰Zr targets, bombarded with protons are calculated based on the nuclear theoretical models. Monte Carlo calculations with the TALYS 1.6 nuclear reaction simulation code are performed. Theoretical calculated results are compared with existing experimental data in EXFOR library.
20
Content available remote

Comparison of Excitation Functions of Longer and Shorter Lived Radionuclides

81%
Noori S., Akkurt İ., Demır N.
Acta Physica Polonica A
|
2017
|
vol. 132
|
issue 3
1186-1188
EN
Nuclear reactions, which are very important from the point of view of human health, may occur during the production of the radiation sources, used in radiotherapy. The nuclear reaction data are needed in the radioisotope production procedure. The total cross section is also important in accelerator technology, in view of radiation protection and safety. In general, the significance of the cross section data for nuclear reactions in radionuclide production programs is firmly established. Gamma irradiation tracers can offer a large amount of information about the anatomy of different organs in the human body. The main purpose of this work was to compare the cross section of longer-shorter lived radionuclides. Theoretical excitation functions have been calculated with TALYS 1.6 nuclear reaction simulation code. The calculated results have been discussed and compared with the experimental data.
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