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EN
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.
EN
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.
EN
Since the technology concerning gamma radiation showed a rapid development, it became a necessity to be protected from it. One of the common shielding materials for this purpose is concrete. This study aims to give the effect of pumice rate on the gamma radiation attenuation coefficients of normal concrete (ρ = 2.476 g cm^{-3}) containing different rates of pumice mineral. Pumice, for which the Gölcük region in Isparta province is rich, is a volcanic originated spongy and porous mineral. Although it is a light material, it has a high comprehensive strength and heat resistance. So it became a common construction material in buildings. In the study, the variation of attenuation coefficients for concretes of different pumice rates were measured for 662, 1173 and 1332 keV photons using a NaI(Tl) detector. The experimental values were compared with the theoretical ones obtained by XCOM code.
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