Browsing by Author "Arasoglu, Ali"

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Calculation of Photo-Nuclear Reaction Cross Sections for 16o
(E D P Sciences, 2015) Arasoglu, Ali; Ozdemir, Omer Faruk
Because of the high thermal expansion coefficient of uranium, the fuel used in nuclear power plants is usually in the form of UO2 which has ceramic structure and small thermal expansion coefficient. UO2 include one uranium atom and two oxygen atoms. After fission progress, total energy values of emitted gamma are about 14 MeV. This gamma energy may cause transmutation of O-16 isotopes. Transmutation of O-16 isotopes changes physical properties of nuclear fuel. Due to above explanations, it is very important to calculate photo-nuclear reaction cross sections of O-16. In this study; for (gamma,p), (gamma,np), (gamma,n) and (gamma,2n) reactions of O-16, photo-nuclear reaction cross-sections were calculated using different models for pre-equilibrium and equilibrium effects. Taking incident gamma energy values up to 40 MeV, Hybrid and Cascade Exciton Models were used for pre-equilibrium calculations and Weisskopf-Ewing (Equilibrium) Model was used for equilibrium model calculations. Calculation results were compared with experimental and theoretical data. While experimental results were obtained from EXFOR, TENDL-2013, JENDL/PD-2004 and ENDF/B VII.1 data base were used to get theoretical results.
(N,p), (N,2n), (N,d), and (N,α) Cross-Section Calculations of 16o With 0-40 Mev Energy Neutrons
(E D P Sciences, 2015) Ozdemir, Omer Faruk; Arasoglu, Ali
Oxygen is one of the elements which interacts with emitted neutrons after fission reactions. Oxygen exists abundantly both in nuclear fuel (UO2) and moderators (H2O). Nuclear reactions of oxygen with neutrons are important in terms of stability of nuclear fuel and neutron economy. In this study, equilibrium and pre-equilibrium models have been used to calculate (n,p), (n,d), (n,2n) and (n,alpha) nuclear reaction cross-sections of O-16. In these calculations, neutron incident energy has been taken up to 40 MeV. Hybrid and Standard Weisskopf-Ewing Models in ALICE-2011 program, Weisskopf-Ewing and Full Exciton Models in PCROSS program, and Cascade Exciton Model in CEM03.01 program have been utilized. The calculated results have been compared with experimental and theroretical cross-section data which are obtained from libraries of EXFOR and ENDF/B VIII.1.
Neutron Cross Section and Emission Spectra Calculations of Na Nucleus
(Springer, 2014) Arasoglu, Ali; Ozdemir, Omer Faruk
Flibe (Li2BeF4) and Flinabe (LiFNaFBeF2) are molten salt which are used as a first wall and blanket in advanced power extraction. Since they have low vapor pressure at high temperature and don't pollute plasma. Moreover, they are used as a coolant material due to their high thermal cycling capacity. There are lots of benefits of using liquid wall such as reducing cost, increasing the reactor power and extending the life time of first steel wall. Being in Flinabe (LiFNaFBeF2) molten salt, (23) Na is also considered as a coolant material in fast reactors. Therefore, the reaction including neutron and (23) Na is getting important. In this study, the cross section calculations of neutron induced reactions for (23) Na were performed. Using pre-equilibrium and equilibrium models, excitation functions of (23) Na(n,p)(23) Ne, (23) Na(n,d)(22) Ne, (23) Na(n,alpha)(20) F, (23) Na(n,2n)(22) Na reactions and (23) Na(n,x alpha), (23) Na(n,xn) emission spectrums were calculated. We calculated alpha emission spectrum obtained when (23) Na nuclei projectiled with 14.1 MeV neutrons and also neutron emission spectrum emitted when (23) Na nuclei was bombardment with 14.6 MeV neutrons.
Neutron Multiplicity With 1.0 and 1.2 Gev Proton-Induced Spallation Reactions on Thin Targets
(Physical Soc Republic China, 2008) Demirkol, Iskender; Arasoglu, Ali; Tel, Eyyuep
In this study, the neutron multiplicity per incident proton in the collision of 1.0 and 1.2 GeV energetic proton beams with Bi, An, Pb, W, Th, Hg, U, Fe, and Cu thin targets has been estimated using the cascade exciton model (CEM), the intranuclear cascade (INC) model, and the evaporation model. The calculations have been compared with the available data. Results obtained using ISABEL-PACE2 come mostly from the evaporation process. The CEM model used in this study does not give results in good agreement with the data.
Photon Attenuation Properties of Some Concretes Containing Barite and Colemanite in Different Rates
(Pergamon-elsevier Science Ltd, 2013) Oto, Berna; Gur, Aycan; Kacal, Mustafa Recep; Dogan, Bekir; Arasoglu, Ali
Radiation shielding properties of concretes containing barite and colemanite in different rates were evaluated by using Ba-133 (80.99 and 303 key) and Am-241 (59.54 key) radioactive sources. Gamma rays were counted by a NaI(TI) detector with a resolution of 122 keV at 662 key. The study reveals that the concretes under research are effective than ordinary concrete for the attenuation of gamma rays. It was determined that the values of mean free path decreased with the increasing concentration of barite and colemanite and the linear attenuation coefficients increased with the increasing concentration of barite and colemanite in the concrete. Theoretical values were obtained by using Penelope and WinXCom computer programs and these were compared with the experimental results. (C) 2012 Elsevier Ltd. All rights reserved.