Yazar "Tel, Eyyup" seçeneğine göre listele

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    Öğe
    A study on nuclear properties of Zr, Nb, and Ta nuclei used as structural material in fusion reactor
    (E D P Sciences, 2015) Sahan, Halide; Tel, Eyyup; Sahan, Muhittin; Aydin, Abdullah; Sarpun, Ismail Hakki; Kara, Ayhan; Doner, Mesut
    Fusion has a practically limitless fuel supply and is attractive as an energy source. The main goal of fusion research is to construct and operate an energy generating system. Fusion researches also contains fusion structural materials used fusion reactors. Material issues are very important for development of fusion reactors. Therefore, a wide range of fusion structural materials have been considered for fusion energy applications. Zirconium (Zr), Niobium (Nb) and Tantalum (Ta) containing alloys are important structural materials for fusion reactors and many other fields. Naturally Zr includes the Zr-90 (%51.5), Zr-91 (%11.2), Zr-92 (%17.1), Zr-94 (%17.4), Zr-96 (%2.80) isotopes and Nb-93 and Ta-181 include the Nb-93 (%100) and Ta-181 (%99.98), respectively. In this study, the charge, mass, proton and neutron densities and the root-mean-square (rms) charge radii, rms nuclear mass radii, rms nuclear proton, and neutron radii have been calculated for Zr87-102, Nb-93,Ta-181 target nuclei isotopes by using the Hartree-Fock method with an effective Skyrme force with SKM*. The calculated results have been compared with those of the compiled experimental taken from Atomic Data and Nuclear Data Tables and theoretical values of other studies.
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    Öğe
    Cross Section Calculations of Neutron Induced Reactions on 124,126,128,134,136Xe
    (Springer, 2015) Kara, Ayhan; Yigit, Mustafa; Korkut, Turgay; Tel, Eyyup
    In the nuclear energy applications Xenon is a desirable material because of its high molecular weight and inert nature. The cross section calculations of Xe-124(n,2n)Xe-123, Xe-126(n,2n)Xe-125, Xe-128(n,2n)Xe-127, Xe-134(n,2n)Xe-133 and Xe-136(n,2n)Xe-135 reactions were performed by ALICE/ASH (with Weisskopf-Ewing equilibrium model), TALYS 1.6 (with two component exciton model suggested by Kalbach) and EMPIRE 3.2 Malta (with exciton model recommended by Clinev and Ribansky) nuclear reaction codes. In addition, semi-empirical cross section formula of Tel et al. was used to obtain cross sections at 14-15 MeV energy. Obtained results were compared to available experimental data by EXFOR database and TENDL-2013 data.
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    Öğe
    Monte Carlo Simulations of 17.9-22.3 MeV Energetic Proton Irradiation Effects on bcc-Zirconium Fusionic Materials
    (Springer, 2016) Korkut, Hatun; Korkut, Turgay; Kara, Ayhan; Yigit, Mustafa; Tel, Eyyup
    Advanced fusion structural materials (FSMs) have impact role in terms of efficiency of nuclear energy production. Besides engineering and design of fusion reactors, radiation durability of FSMs is another valuable issue that cannot be ignored. 17.9-22.3 MeV proton irradiation of bcc-Zirconium Fusion Structural Material was evaluated by using Monte Carlo based simulation tools. Total binary reaction cross sections were respectively calculated as 1167.6 and 1273.92 mb for 17.3- and 22.3 MeV proton energies via TALYS-1.6 version. Additionally, residual production cross sections and total particle production cross sections were obtained and analyzed by the TALYS code. Radiation damage parameters as Displacement Per Atom (DPA) and Stopping Power (SP) were studied by SRIM-2013 version. FLUKA 2011.1 used for only DPA calculations and making a complete comparison with the other calculation results. SP and Number of Secondaries were found by using GEANT4.10.p.04 version simulations. Natural Zr(p,x) reactions were studied in the given energy values in the plane of reaction probability and radiation damage calculations.
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    Öğe
    Spatial distribution of 222Rn concentrations and dose estimations in various waters
    (Taylor & Francis Inc, 2016) Erdogdu, Murat; Damla, Nevzat; Kara, Ayhan; Sahan, Halide; Isik, Umit; Tel, Eyyup; Sahan, Muhittin
    In this article, the levels of Rn-222 concentrations, annual effective doses, and excess lifetime cancer risk estimations were investigated for water samples in the city of Osmaniye, located in the southern part of Turkey. The measurements were conducted using a radon gas analyzer (AlphaGUARD PQ 2000 PRO). The arithmetic average of Rn-222 concentrations was 0.44 Bq.L-1 with a geometric standard deviation of 0.19 and geometric average 0.41Bq.L-1. The results obtained were compared with the findings of other studies. All measured radon concentrations were below the values recommended by the World Health Organization and the U.S. Environmental Protection Agency. The associated radiological parameters such as annual effective doses (AED) and excess lifetime cancer risk (ELCR) from consumption of these waters were calculated. The computed average annual effective doses for ingestion and inhalation as well as excess lifetime cancer risk were estimated to be 1.13 mu Sv.y(-1), 1.10 mu Sv.y(-1), and 3.95 x 10(-6), respectively. Rn-222 concentration, AED, and ELCR interpolated values of the region were determined and mapped using the Kriging method. The results of radon concentrations in this study provide a data baseline for future studies on subsequent evaluations of possible future environmental contamination of Osmaniye Province.