Theoretical studies via nuclear reaction models have an undeniable importance and impact in terms of better understanding of reaction processes and their nature. In this study, by considering the importance of these models and the medical radionuclides, the effects of six level density models and eight alpha optical model potentials on the cross-section calculations for the production of the radionuclides ⁶²Cu, ⁶⁷Ga, ⁸⁶Y and ⁸⁹Zr via ⁵⁹Co(α,n)⁶²Cu, ⁶⁰Ni(α,np)⁶²Cu, ⁶⁵Cu(α,2n)⁶⁷Ga, ⁶⁴Zn(α,p)⁶⁷Ga, ⁸⁵Rb(α,3n)⁸⁶Y, ⁸⁶Sr(α,n)⁸⁹Zr, ⁸⁷Sr(α,2n)⁸⁹Zr and ⁸⁸Sr(α,3n)⁸⁹Zr reactions were investigated. Calculations for each reaction route were performed by using the TALYS v1.9 code. The most consistent model with the literature data taken from the Experimental Nuclear Reaction Database (EXFOR), was identified by using the reduced chi-squared statistics in addition to an eyeball estimation. Also, the effects of combinational use of selected models and potentials were investigated by comparing the calculational results with the experimental data.

In this research, the calculations have been done for α-emitters of ²¹¹At, which is a promising isotope in cyclotrons for radiotherapy. The scope of the study is to investigate the production parameters of ²¹¹At, which can be produced in the cyclotron by bombarding bismuth with an alpha particle beam for the ²⁰⁹Bi(α,2n)²¹¹At reaction. The total activity, reaction yield, and production cross–sections of ²⁰⁹Bi(α,2n)²¹¹At reaction have been calculated by using diverse level density models of the TALYS 1.95 code. Furthermore, recommended data with 95% confidence limits have been obtained. Experimental data available in the literature based on EXFOR compilation are used to compare the findings. Consequently, the required beam energy has been found to be 28 MeV to produce ²¹¹At.

The employment of the fusion mechanism for the energy production is a promising solution to the continuously growing global energy demand. The correct mate

One possible solution to the increasing energy demand, which mankind has been facing through, might be pointed as the nuclear reactors that work with the fission mechanism. In order to pursue the operation of these facilities, many equipment have been designed in a way that all of them could operate together where the control rods could be given as one of the vital parts among them. Material properties of these components, such as physical-chemical characteristics and their behaviors under different interactions, have an undeniable importance. Due to that, gathering all the possible information about the materials used for the production of these components is extremely important. By considering this importance, in this study, the mass stopping power and charged particle penetration distance calculations have been done for some materials which have possible usage in nuclear reactor control rods using alphas, 3He, tritons, deuterons and protons within the energy range of 1-50 MeV via employing two of the most known computer aided calculation and simulation software which are GEANT4 and MCNP. Obtained results from both codes have been visualized by graphing and compared with each other.