Nuclear level density is a fission characteristics for each core. Level density parameter ratio a_{f}/a_{n} plays an important role in the statistical calculations of the fission, investigation of heavy ion collisions and calculation of the reaction cross sections. In this study, the effects of the different level density ratio on the fission reaction cross section for uranium isotopes were investigated. Calculations were carried out using the Monte Carlo simulation codes ALICE/ASH and TALYS 1.6. The calculated results were compared with the experimental reaction cross sections from literature.
Myocardial perfusion scintigraphy, is an imaging technique used for diagnostics of coronary artery disease in people by evaluating the amount of blood reaching the heart muscle. During myocardial perfusion scintigraphy a radiopharmaceutical is injected into the patient and after a period of time a series of images are acquired using gamma camera rotated by 180° around the patient. The distribution of the radiopharmaceutical is then determined using the technology of single photon emission computed tomography. The most commonly used agents in myocardial perfusion scintigraphy radiopharmaceuticals are Tl-201 and Tc-99m. The production of such radiopharmaceuticals containing Tl-201 and Tc-99m has been examined by this study. This study was performed using Monte Carlo nuclear reaction simulation code TALYS 1.6.
Knowledge of the cross sections of reactions of charged particles with target material is needed to understand well the mechanisms of nuclear reactions. One of the main application fields of nuclear technology and nuclear reactions is medicine. Radioisotopes are used in medicine and production of these radioisotopes is important. In the production processes, the cross sections must be known. For this purpose, in this study, theoretical cross sections of production of In isotopes by alpha irradiation have been calculated using Talys 1.6 nuclear reaction simulation code. The obtained results are compared with the existing experimental data.
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.
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.
Many radioisotopes are used in nuclear medicine diagnostics and therapy. Co-57, In-111 and Tc-99m isotopes are widely used in nuclear medicine and are successfully implemented in renal imaging. In this work, the cross section calculation of the (p, 2n) reaction, which is necessary for production of the nuclei of Co-57, In-111, Tc-99m, were calculated using TALYS 1.6 nuclear reaction code. The calculated cross sections were compared with the experimental data from the EXFOR.
Positron emission tomography is an imaging method which plays an important role in the diagnosis and monitoring of cancer cells using radioactive substances. In this study (p,n) reaction cross sections of some radionuclides (Cu-61, Ga-66, Br-76) were calculated using Talys 1.6 nuclear simulation code. The calculated cross-sections were compared with experimental values taken from EXFOR.
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.
Photonuclear processes can play an important role in the detection of nuclear materials. For this purpose, in this study, the (γ,n) and (γ,p) cross sections as functions of photon energy in medium weight nuclei were calculated. Calculations have been made of the cross sections for some of the (γ,n) and (γ,p) reactions in ^{28}Si, ^{32}S, ^{56}Fe and ^{63}Cu nuclei using the TALYS 1.6 nuclear code with incident photons of 7-40 MeV. These calculated cross sections are compared with each other and with the earlier experimental results from the literature (EXFOR). Calculated results (^{56}Fe(γ,n), ^{63}Cu(γ,n), ^{56}Fe(γ,p) and ^{63}Cu(γ,p) cross sections) are in very good agreement with the experimental data. However, because of the Coulomb barrier, the photoproton cross sections for ^{32}S, ^{56}Fe and ^{63}Cu target nuclei, are smaller than the photoneutron cross sections.
Photonuclear reactions play an important role in many different subfields of nuclear astrophysics, and fields, such as nucleosynthesis applications. The photonuclear reaction cross sections, especially the photoneutron reaction cross sections, are the fundamental properties of nuclear systems. In this study, theoretical evaluation of photoneutron reaction cross sections for 27 ≤ A ≤ 238 targets (^{27}Al, ^{96}Mo, ^{181}Ta, ^{238}U) have been investigated in the incident photon energy range of 7-35 MeV. Monte Carlo code TALYS 1.6 was used to calculate the photoneutron cross sections. The results are compared with the earlier experimental reports in literature and the cross section data in the TENDL-2013 nuclear reaction data library, based on subsequent versions of the TALYS nuclear code system. The photoneutron cross section results and the effects of the mass number of target nuclei are discussed.
During the production of the radiation source that used in radiotherapy may occur nuclear reactions are very important in terms of human health. ^{137}Cs is used in radiotherapy that consists of fission the ^{235}U core. Because of physical half-live of ^{137}Cs is 30 years, it is advantage for the radioactive half-lives. In this study, radionuclide production reaction cross section for ^{235}U (n,f)^{137}Cs is calculated with TALYS 1.6 nuclear simulation code that based on Monte Carlo.
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