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The purpose of this study to examine experimentally self-absorption correction factors (SACFs) of some algae samples using gamma-ray spectrometry. Various algae samples were collected from Boğaçay in Antalya, Turkey. Collected algae samples were dried, and masses of the samples were calculated. Then densities of the samples were calculated. Each of algaes was counted with and without point sources which are 22Na, 60Co, 133Ba, and 137Cs about 1000 seconds using high purity germanium detector. The SACFs of algae samples were calculated between 80 keV and 1332 keV gamma-ray energies. As a result, SACFs of studied algae samples generally reduce as gamma-ray energy enhances. SACFs of some algae samples are nearly steady because of the densities and elemental contents of the studied algaes.

The aim of this study is to investigate the activity concentrations of 226Ra, 232Th, 40K and 137Cs in soil samples from Seydisehir and Beysehir districts of Konya province in Turkey using gamma-ray spectrometry and to calculate radiological risk parameters. The average radioactivity concentrations of 226Ra and 232Th are higher than world average value whereas the average radioactivity concentration of 40K is lower than world average value. Mean values of absorbed gamma dose rate and annual effective dose equivalent are higher than world mean value while mean value of radium equivalent activity is lower than world average value.

Tellurite glass systems become an essential component for several medical and nuclear technologies. Radiation shielding characteristics of a newly developed tellurite glasses containing Sb2O3 and V2O5 in energy range from 0.1 to 10 MeV are reported in this work. A FLUKA simulation along with a suitable theoretical model is carried out to examine the shielding performance of the involved glass system against gamma, neutron, and charged-particles radiations. HVLs of the TSP glasses vary in order of TSP-D

The goal of this study is to examine theoretically radiation absorption properties of zinc alumino bismuth borate (BZnAlBiSm) glasses with chemical formula 60B2O3-9ZnO-(30-x)Al2O3-xBi2O3-1Sm2O3 where x = 5, 10, 15 and 20 mol%. The linear and mass attenuation coefficents of BZnAlBiSm glasses turn out as this trend BZnAlBiSm-1

For safe immobilization of nuclear waste, lead-iron phosphate glasses are promising as high-level commercial and defense materials. In this research article, the compositional, elastic, and gamma shielding properties of the glasses containing (80 − x)P2O5– xFe2O3–20PbO with x = 20, 25, 30, 35 mol% were reported. The compositional and elastic parameters including the micro-hardness of the investigated glass samples were obtained based on Makishima-Mackenzie’s theory (MM-theory) and R model. We found that the deviation between these two methods decreased as Fe2O3 concentrations increased from 20 to 35 mol %. Additionally, γ-ray attenuation properties of the P2O5– Fe2O3–PbO glass system were evaluated using Geant4 simulation toolkit. The simulation results were compared with the theoretical ones extracted from Py-MLBUF software. The obtained results reveal that the MACs of the glasses vary from 0.030 to 40.014 cm2/g for PFP-A, from 0.031 to 41.502 cm2/g for PFP-B, 0.031 to 43 cm2/g for PFP-C and from 0.031 to 44.400 cm2/g for PFP-D. Maximum Zeff values of present glasses are obtained at 0.10 MeV whereas minimum Zeff values are obtained at 1.5 MeV. Finally, the fundamental γ-ray attenuation properties of the P2O5– Fe2O3–PbO glass system are found to be comparable with those of traditional and commercial radiation shields such as RS-253-G18 and RS-360 commercial glasses, ordinary concrete, barite concrete and TBZP10 from scientific literature. The results indicated that MFPs of the investigated glasses are lower than those of RS-360 glass, but they are higher than those of barite concrete and TBZP10.

Tobacco samples were collected from different tobacco markets from Antalya in Turkey. To calculate natural radionuclides activity concentration, samples were counted for 86400 seconds by using high purity germanium (HPGe) detector. Activity concentrations of 226Ra, 232Th and 40K for tobacco samples found higher than minimum detectable activity (MDA). 137Cs was not detected in any sample. Activity concentration of 226Ra, 232Th and 40K range from 83±15 Bqkg-1 to 325±45 Bqkg-1, 29±5 Bqkg-1 to 207±37 Bqkg-1 and (2.09±0.28)x103 Bqkg-1 to (5.07±0.90) x103 Bqkg-1, respectively. In addition, annual effective dose value was calculated. The annual effective dose values owing to inhalation for adults change from 2.76 to 9.91 µSvy-1 for 214Pb, from 5.69 to 27.69 µSvy-1 for 214Bi, from 5.72 to 40.41 µSvy-1 for 228Ac, from 42.23 to 102.37 µSvy-1 for 40K. The total annual effective dose values change from 0.05 to 0.16 mSvy-1.

In the present investigation, mass attenuation coefficients ( μ m ) and some related nuclear shielding quantities of various granite samples have been computed at several photon energies of 0.356, ...

The purpose of this study is to calculate self-attenuation correction factors, linear (LAC) /mass attenuation coefficients (MAC), half value layers (HVL) and tenth value layers (TVL) of different brands of commercial salt samples using gamma-ray spectrometry equipped with high resolution germanium (HpGe) detector. The gamma-rays emissions of 22Na, 60Co, 133Ba and 137Cs point sources were counted with/without sample. The obtained gamma-ray spectra were analyzed using computer software. Self-attenuation correction factors and gamma-ray attenuation parameters of eleven different brands of commercial salt sample were calculated. The experimental MACs of salt samples were compared with those of NaCl compound utilizing WinXCom software.

We investigated the natural and artificial radioactivity levels of soil samples from Saklikent, Antalya due to the radioactive isotopes of 238U, 232Th, 40K and 137Cs via gamma spectroscopy. While 137Cs is the only contributor of artificial radioactivity, the rest of the isotopes contributes natural radioactivity. Absorbed dose rates, radium equivalent activities, annual effective dose equivalents and internal and external hazard indexes are also calculated from measured levels. Results were compared with reported limit values of literature. Anomalies were observed in the activity concentration of the 238U, 232Th and 40K. It is concluded that these anomalies explicitly come from the quarries. On the other hand, the anomaly observed in 137Cs is clearly dependent on the fallout from nuclear accidents like Fukushima. This study will be a useful reference for literature, especially after a nuclear plant is established in Mersin, Akkuyu region of Turkey.

International audience; The possibility to use a special class of heavy-ion induced direct reactions, such as double charge exchange reactions, is discussed in view of their application to extract information that may be helpful to determinate the nuclear matrix elements entering in the expression of neutrinoless double beta decay half-life. The strategies adopted in the experimental campaigns performed at INFN - Laboratori Nazionali del Sud are briefly described, emphasizing the advantages of the multi-channel approach to nuclear reaction data analysis.

Çevresel radyoaktivite genellikle doğal radyasyon ve yapay radyasyon olarak iki kısımda oluşmaktadır. Yapay radyasyon; nükleer silah denemeleri, nükleer kazalar, nükleer tıp uygulamaları ve parçacık hızlandırıcılar sonucunda meydana gelmektedir. 2011 yılında Fukushima Daiichive 1986 yılında Çernobil’ de meydana gelen nükleer santral kazaları sebebiyle çevreye yoğun miktarda yapay radyoaktif nükleotitler saçılmıştır. Çernobil nükleer kazası İstanbul’ a yakın olduğu için, radyoaktif serpintiden etkilenme olasılığı yüksektir. Bu çalışma İstanbul’un Sarıyer ilçesinde bazı toprak örneklerinde yapay radyoaktif madde olan Cs-137 konsantrasyonun belirlenmesi amacıyla yapılmıştır. Çalışma bölgesinde 12 örnekleme noktası belirlenmiş, spektroskopik ölçümler, yüksek saflıkta germanyum detektör (HPGe) ile yapılmıştır. Cs-137 radyoaktivite konsantrasyonları 1.70 ± 0,72 Bqkg-1 ile 16.43±1.26Bqkg-1 arasında değiştiği bulunmuştur.

Çay, sudan sonra dünyada en çok tüketilen ikinci bitki türüdür ve nemli iklimlerde yetiştirilir. Tüketim sıklığı göz önüne alındığında çay bitkisinin hem ticari hem de halk sağlığı açısından çok önemli bir çalışma alanı haline gelmesi kaçınılmazdır. Çay bitkisi, üretim şekline göre yeşil çay, siyah çay, oolong çayı ve beyaz çay olmak üzere dört farklı biçimde karşımıza çıkar. Özellikle beyaz çay, antioksidan etkisi nedeniyle son yıllarda bilimin ilgisini çekmeye başlamıştır. Bu çalışmanın amacı, Türkiye'de Karadeniz Bölgesi’nden toplanan siyah ve beyaz çayın radyonüklitlerini ve elementel konsantrasyonlarını incelemektir. İncelenen örnek çayların doğal ve yapay radyonüklid konsantrasyonları gama ışını spektrometresi kullanılarak belirlendi. Hem siyah hem de beyaz çay örneklerinde 226Ra, 232Th, 40K, 137Cs konsantrasyon seviyeleri tespit edildi. Siyah ve beyaz çayın elementel konsantrasyonları, enerji ayırımlı x-ışını floresans (EDXRF) spektrometresi kullanılarak belirlendi. Siyah ve beyaz çay örnekleri için taramalı elektron mikroskobu (SEM) mikrografları elde edildi. Siyah çayın 226Ra ve 137Cs aktivite konsantrasyonları beyaz çaydan daha yüksek olduğu, ancak beyaz çayın 232Th ve 40K aktivite konsantrasyonlarının siyah çaydan daha yüksek olduğu görülmüştür. Beyaz çayın toplam doz değeri siyah çaya göre daha yüksek olduğu belirlenmiştir., Tea is the second most consumed plant worldwide after water and it can be grown in humid climates. Considering the frequency of consumption, it is inevitable for the tea plant to become a very important field of study both in terms of commercial and public health. The tea plant appears in four different forms which are green tea, black tea, oolong tea and white tea depending on the production method. Especially white tea has started to attract the attention of science in recent years due to its antioxidant effect. The aim of this study is to examine radionuclides and elemental concentrations of black and white tea collected from Karadeniz in Turkey. Natural and artificial radionuclides concentrations were determined using gamma-ray spectrometry. 226Ra, 232Th, 40K, 137Cs were detected in both black and white tea samples. Elemental concentrations of the black and white tea were determined using energy dispersive x-ray fluorescence (EDXRF) spectrometry. Scanning electron microscopy (SEM) micrographs were obtained for black and white tea samples. 226Ra and 137Cs activity concentrations of black tea are higher than white tea however 232Th and 40K activity concentrations of white are higher than black tea. Total dose value of white is higher than black tea.