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)
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.
Radiation is used different field and among others neutron is the one of the most hazardous particle as it is neutral and heavy. Its neutral characteristics make it more difficult particle to be shielded. In this study neutron shielding properties for some medical interested materials of water, fat and bone have been obtained using Phy-X/PSD software.
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 12 C 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.
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