Full-text resources of PSJD and other databases are now available in the new Library of Science.
Visit https://bibliotekanauki.pl
Preferences help
enabled [disable] Abstract
Number of results

Results found: 10

Number of results on page
first rewind previous Page / 1 next fast forward last

Search results

help Sort By:

help Limit search:
first rewind previous Page / 1 next fast forward last
EN
Environmental wastes can be cleaned in a very long time by ecosystem. However, the cleaning power of the ecosystem is not enough. For this reason, the evaluation of the different areas of waste processing is important. In this study attenuation coefficient of gamma rays has been investigated for concretes containing different amounts of glass, bulb and plastic wastes.
EN
In this study, the radiation absorption properties of mortars and plasters used in historical buildings have been investigated. Studied lime concretes contained such additives as brick dust, fertilizer, wet lime, wool, egg white, bone meal, rice, casein, whey, bone ash and tree leaf juice, in different concentrations. The linear attenuation coefficients of gamma rays in lime concretes have been measured at 662, 1773 and 1332 keV. The gamma rays have been obtained from ¹³⁷Cs and ⁶⁰Co sources and the measurements have been performed using a gamma spectrometer, based on a 3"× 3" NaI(Tl) detector, connected to 16384-channel multi-channel analyser.
EN
People are exposed to both internal and external radiation from the natural radiation sources. For this reason, studies determining the natural radiation level are made to detect the effects of radionuclides, that constitute the natural radiation sources, on the environment and especially the effects of radiation on people and on biological systems. The most common radiation sources are ²³⁸U, ²²⁶Ra, ²³²Th and ⁴⁰K radioisotopes. In this study, in the samples of the rock and soil acquired from Amasya Şeyhcui Region, the activity concentrations of ²²⁶Ra, ²³²Th and ⁴⁰K are determined by using NaI (Tl) detector with gamma spectrometer and are compared with the limit values.
EN
In nuclear reactions the usage of high energy gamma particles, as projectiles, has some essential advantages for studying of nuclear structure and reaction mechanisms. In this work, (γ,n) reaction cross sections of ¹⁸⁶W, ¹⁰⁷Ag and ⁹³Nb have been calculated with TALYS 1.6 nuclear reaction simulation code. The main aim of this study is to investigate the effects of preequilibrium and the gamma strength functions on ¹⁸⁶W, ¹⁰⁷Ag and ⁹³Nb. The calculated results have been discussed and compared with the experimental data.
EN
In general, the deep understanding of proton-induced reactions is a crucial step for the further development of nuclear reactions theory. However there has been an interesting focus in nuclear physics. Some applications require accurate nuclear reaction data of common cross sections and especially need the data of neutron and proton induced energy-angle correlated spectra of secondary particles, as well as double differential cross sections. Double-differential nucleon-production cross-sections of ⁵⁶Fe, ⁶³Cu and ⁹⁰Zr targets, bombarded with protons are calculated based on the nuclear theoretical models. Monte Carlo calculations with the TALYS 1.6 nuclear reaction simulation code are performed. Theoretical calculated results are compared with existing experimental data in EXFOR library.
EN
The concentration of natural radioactivity was determined in the surface soil of the Gözlek Thermal SPA in Amasya. The activity concentrations of natural radionuclides in soil samples were determined using gamma-ray spectrometer, containing a 3"× 3" NaI(Tl) detector connected to multi-channel-analyser. The photo-peaks at 1460, 1764 and 2615 keV are due to ⁴⁰K, ²²⁶Ra and ²³²Th, respectively. The radiological hazard indices of the natural radionuclides content, radium equivalent activities Ra_{eq}, absorbed dose rate (ADR), annual effective dose rate (AEDR) and external hazard index H_{ex} were also calculated.
EN
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.
EN
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.
EN
In this study, radiation shielding properties of soda-lime-silica glasses doped with different food materials such as the egg shell and the peanut shell powders were investigated. Egg shell and peanut shell powders were obtained by grinding of waste shells in an agate mortar. The SLS glass samples with varying egg shell/peanut shell content were produced by melting. The measurements have been performed using the gamma spectrometer, containing a 3" × 3" NaI (Tl) detector, and connected to a full featured 16K channel Multi Channel Analyzer provided by ORTEC/MAESTRO-32 software.
EN
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.
first rewind previous Page / 1 next fast forward last
JavaScript is turned off in your web browser. Turn it on to take full advantage of this site, then refresh the page.