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137Cs chemical precipitation in water samples with ammonium phosphomolybdate (AMP) method and chemical yield calculation by XRF technique
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Başsarı, Asiye; Kaygun, Aysun; Yılmaz, Y. Z.; Yüksel, A.; TAEK-ÇNAEM
210Po distribution in hydrothermal vent zone at Gülbahçe, Aegean Sea
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Sert, İ.; Yener, G.; Uğur, A.; Pişkin, A.; Özel, E.; Eftelioğlu, M.; Pekçetinöz, B.; 45035; Bölüm Yok
7Be and 137Cs in lichen and soil samples
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Azimov, A. N.; Muminov, I. T.; Muhamedov, A. K.; Safarov, A. A.; Safarov, A. N.; Bölüm Yok
99Mo/99mTc generator and radiopharmaceuticals productions at Çekmece Nuclear Research and Training Center
(Turkish Atomic Energy Authority, 2000-10) Bodur, Nazan; Yıldız, Hülya; Ergün, Aysun; Bostan, Nilgün; Akşit, Makbule; Ayyıldız, Hayrettin; Saygı, Nur; Göçer, Beytullah; TAEK-ÇNAEM
Molybdenum-99 is produced in large quantities as the parent radioisotope of " mTc, which has been used in nuclear medicine. The rapid growth of nuclear medical diagnosis with " mTc is due to completion of a system supplying radiopharmaceuticals labelled with a short lived radioisotope like " mTc, and the development of nuclear medical instruments like an Anger Camera and a single photon emission tomography (SPECT or ECT). The Radioisotope and Radiopharmaceutical Department (RIF) at Çekmece Nuclear Research and Training Center (ÇNAEM) has been active in production of " mTc and kits to be labelled to form radiopharmaceuticals. In generator produced eluates, the purity and chemical parameters must conform to special requirements. The requirements of European Pharmacopoeia for sodium pertechnetate " mTc injection are fulfdled when it is prepared in our department. Assurance of radiopharmaceutical quality control, which involve test of biolog ical purity and pyrogenity and sterility, is also performed
A comparative study on neutron-gamma discrimination with UGF and UGAB scintillators
(Azerbaijan National Academy of Sciences Institute of Radiation Problems of ANAS, 2014-10) Divani, N.; Firoozabadi, M. M.; ABF-7403-2021; 0000-0003-0561-9040; Bölüm Yok
A complex of equipment for preparation of high-quality radioactive sources used in precise nuclear spectroscopy
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Aldiyarov, N. U.; Kadyrzhanov, K. K.; Zhdanov, V. S.; Bölüm Yok
A finite element formulation for perturbation theory calculations
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Özgener, B.; Kaluç, S.; 149220; Bölüm Yok
A gamma spectrometric method for direct measurement of uranium contents in solid samples
(Turkish Atomic Energy Authority, 2000-10) Yücel, Haluk; Ergin, İ.; Çetiner, M. Atıf; Demirel, Halil; Tan, M.; Özmen, Atilla; 3905; TAEK-ANAEM
A gamma spectrometric method is described for the direct “absolute” determination of uranium contents in solid samples. To obtain the exact information about the measurement of 238U in samples by gamma-ray spectroscopy, it is essential that any one of the daughters of 238U should exist in radioactive equilibrium with 238U. This condition is mainly fulfilled by one of the first two daughters, namely, 234Th (24.1 d) and 234mPa (1.17 min) because these daughters are very short-lived compared with 238U. Therefore, the present analytical method employs direct determination of U via the 63.3 keV gamma emission from Th and via the 1001 keV gamma emission from 234mPa. The absolute photopeak efficiency data in the range of 40 keV to 2000 keV for the reverseelectrode Germanium(REGe) detector used is measured using a powder radioactive standard source. The certified uranium samples were prepared in thin thicknesses to minimize the selfabsorption of gamma rays. They are counted for the the time predetermined between 75,000 s and 125,000 s. The measured activities of 238U of the samples via the 63.3 keV (234Th ) and via the 1001 keV (234mPa) are corrected for self-absorption effects due to changes in composition of standard reference materials in a given sample-detector geometry. The self-absorption factors applied to the 46.5 keV(210Pb) peak and the 63.3 keV(234Th) peak results ranged from 10.5% to 33.1% and from 4.9% to 18.4%, respectively. For the 1001 keV(234mPa) gamma emission, the necessary self-absorption factors varied between 0.1% and 3.9%. The results obtained from the 46.5 keV of Pb being far distant member of U and those of the 63.3 keV from 234Th are used to check whether the equilibrium exist in the uranium samples. The results of U via the 63.3 keV peak of Th for the uranium standards agreed to within 0.1 to 6.9% with the certified values of 238U in the samples with uranium concentration ranging from 0.022±001 to 1.02±0.01 wt%. The results of 238U via the 1001 keV peak of 234mPa agreed well to within 0.01 to 4.7% with the certified activity values of 238U of the same samples. When the measurements of the uranium are carried out in a REGe detector system, the results indicate that the uranium concentrations in the samples can be determined to the average 7% error by using the 63.3 keV(234Th) gamma emission with appropriate corrections for self-absorption effects. The 1001 keV peak of 234mPa gives also accurate results for the determination of 238U in the same samples and the need for self absorption correction for the 1001 keV emission seems to be negligible, except in case of thicker samples than that of 1.5 cm thick.
A general overview and literature review on clearance criteria
(IAEA, 2002-10) Özdemir, Tonguç; Uslu, İbrahim; TAEK-RSGD
A monte carlo investigation of the effect of source geometry variations on brachytherapy seed sources
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Camgöz, B.; Yeğin, G.; Kumru, M. N.; 103959; Bölüm Yok
A neutronic and thermal-hydraulic visual computer code for TR-2
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Erdoğan, Adem; TAEK-ÇNAEM
A new approach for the scattering of deformed light heavy-ions: a challenge to the standard approach
(Turkish Atomic Energy Authority, 2000-10) Boztosun, İ.; 8985; Bölüm Yok
A new approach in the analyses of deformed light heavy-ion reactions has been introduced to explain the experimental data. This new coupled-channels based approach involves replacing the usual first derivative coupling potential by a new, second-derivative coupling potential. This paper first shows and discusses the limitation of the standard coupled-channels theory in the case where one of the nuclei in the reaction is strongly deformed. Then, this new approach is shown to improve consistently the agreement with the experimental data: the elastic and inelastic scattering as well as their 90" and 180" elastic and inelastic excitation functions.
A new standart En 14569: microbiological screening for irradiated food using limulus amoebocyte lysate - gram negative bacteria procedures
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Koluman, Ahmet; Özyardımcı, Berna; TAEK-SANAEM
A review of the probabilistic safety asssessment application to the TR-2 research reactor
(Turkish Atomic Energy Authority, 2000-10) Göktepe, B. Gül; Adalıoğlu, Ulvi; Anaç, Hakan; Sevdik, Bülent; Menteşoğlu, Selim; TAEK-ÇNAEM
A review of the Probabilistic Safety Assessment (PSA) to the TR-2 Research Reactor is presented. The level 1 PSA application involved: selection of accident initiators, mitigating functions and system definitions, event tree constructions and quantification, fault tree constructions and quantification, human reliability, component failure data base development, dependent failure analysis. Each of the steps of the analysis given above is reviewed briefly with highlights from the selected results. PSA application is found to be a practical tool for research reactor safety due to intense involvement of human interactions in an experimental facility. Insights gained from the application of PSA methodology to the TR-2 research reactor led to a significant safety review of the system.
A science administrator’s view of the new economy
(Turkish Atomic Energy Authority, 2000-10) Pak, Namık Kemal; 12932; Bölüm Yok
A simple approach for pre-loca analysis of MTR type research reactors
(National Nuclear Center of the Republic of Kazakhstan / Institute of Nuclear Physics, 2003) Yılmazer, Ayhan; Yavuz, Hasbi; 169974; G-6010-2013; TAEK
In this study, it is intended to analyze early phases of a protected loss of coolant accident (LOCA) for TR-2 Research Reactor at Istanbul, and to show the applicability of the presented model to the other similar types of research reactors. The transient situation since the time when coolant is beginning to be lost throughout one or more of the main coolant pipes which were supposed to be broken guillotine-like to the time when the core is totally uncovered is investigated. The modeling of the problem was separated into two phases; in the first phase when the water level of the pool is being decreased in a pre-estimated timedependent way calculated by using Modified Bernoulli Equation, the conservation equations are solved by a usual implicit finite difference algorithm. The later phase, when water level reaches to the top level of fuel plates and begins to decrease until the bottom of the core, needs some modifications to the approach used for the first phase. Because, the coolant channels among fuel plates are filled with air when the level goes below, and the fuel plates are being cooled by air above the water level. This complexity is resolved using a moving boundary approach in the numerical solution. A Lagrange type interpolation approximation for the derivatives along with interface conditions in the neighborhood of the airwater interface was imported to the numerical algorithm. The analysis is performed for a nominal channel.
A statistical study of filtres used as shielding for PC monitors
(Turkish Atomic Energy Authority, 2000-10) Tuğrul, A. Beril; Altınsoy, Nesrin; Ayaz, Birsen; 200243; Bölüm Yok
In this paper it was aimed to obtain a radiological study about the attenuation of radiation of PC fdters which are produced by different companies. For this purpose different radiation sources were used for UV (ultraviolet) IR (infrared), visible light and X-ray radiation. For every type of radiation measurements, the most proper detector was selected. The radiation measurements were made with and without fdters and the measurements were taken for different distances. Measurements have bee observed for white & black and coloured monitors radiation levels for X-ray emission. All results were compared according to related regulations. Furthermore all data evaluated statistically in the point of view of public safety.
A study of carrier collection in GaS - based x-ray and γ-ray detectors by photoelectric method
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Madatov, R. S.; Mehrabova, M. A.; Hasanov, N. H.; Bölüm Yok
A study of the gamma family characteristics produced in AA interactions above 10 Pev
(National Academy of Science of Kyrgyzstan, Turkish Atomic Energy Authority, 2008) Yuldashbaev, T. S.; Nuritdinov, Kh.; Bölüm Yok
A study on passive containment cooling condensers in SBWR
(Turkish Atomic Energy Authority, 2000-10) Kuran, Selim; Sökmen, Cemal Niyazi; Bölüm Yok
The passive containment cooling condensers (PCCC) are the crucial part of several new reactor designs, like European Simplified Boiling Water Reactor (ESBWR) and the SBWR. In a hypothetical accident, the pressurised steam non-condensable mixture from drywell is condensed in PCCCs, and condensate is returned to reactor vessel while non-condensable is vented through wetwell. In this study, in order to examine the performance of PCCCs, condensation with presence of noncondensable is investigated. Condensation with different noncondensable types and conditions is studied on a PCCC model, which is developed by using RELAP5 Mod3.2 computer code

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