Calculation of 89Y(p,x)86,88,89gZr, 86g,87g,88gY, 85gSr, and 84Rb reaction cross sections based on level density

Simulation of the indirect reaction 92Mo(α, 2n)94Ru→m94Tc using TALYS and GEANT4 nuclear codes

Radioisotope 94mTc is a favorable positron emitter radioisotope in nuclear medicine that can be used for PET. Production of 94mTc via indirect reaction 92Mo(α, 2n)94Ru → 94mTc was predicted by SRIM, TALYS,and GEANT4 codes. SRIM and GEANT4 codes were employed to calculate the range of alpha particles into enriched 92Mo and to estimate the thickness of the target. Further, the GEANT4 and the TALYS codes were used to investigate the cross-section and production yield of the 92Mo(α, 2n)94Ru reaction. Four model methods were utilized to compute the cross-section by TALYS-1.95 code. The simulated results were compared with experimental values that reported by F.O. Denzler and found to be in good agreement between them. This observation indicates that the SRIM, the GEANT4 and the TALYS codes are suitable tools for prediction of producing radioisotopes via various reactions.

Effects of some level density models and γ-ray strength functions on production cross-section calculations of 16,18O and 24,26Mg radioisotopes

Oxygen and magnesium isotopes can be used in nuclear reactor materials as cooling, shielding, coating, electronics etc. They can also occur through nuclear reactions during the reactor operation. The exposure of high energy gamma can change the material and its properties, and hence its objective of selection may not remain satisfied. Thus, it is required to study the cross section of different reactions on nuclear reactor materials to understand their sustainability for the properties, for which they are chosen. In the scope of this study, theoretically, different level density model calculations and γ-ray strength functions have been performed for (γ, p) reaction for 16,18O and 24,26Mg nuclei using TALYS 1.9 and EMPI˙RE 3.2.2 codes. Also, semi empirical (γ, p) formula by Tel et al., have been calculated and compared with all results. The effect of different level density models defined in these codes on gamma strength has been studied. Finally, the consistency of these obtained data with EXFOR data have been investigated.

Nuclear model calculations on the production of auger electron emitter 111In: As a theranostic radionuclide

The main goal of this study is the production investigation of the ¹¹¹In as a diagnostic and mighty radionuclide in nuclear medicine especially in the Single Photon Emission Computed Tomography (SPECT) technique. Excitation functions based on four main phenomenological level density models were evaluated for the induced reactions; namely, ¹⁰⁹Ag(α,2n), ¹¹⁰Cd(d,n),¹¹¹Cd(p,n),¹¹²Cd(p,2n),^natCd(p,xn) and ^natCd(d,xn) using the TALYS-1.8 and EMPIRE-3.2 nuclear codes. Furthermore, simulation code was used for the mentioned processes and, also, the ¹¹¹In production yield predictions in each reaction were done. Finally, in order to certify the above calculation outcomes, a comparison with the existing data which were taken from EXFOR database was implemented.