Nuclear model calculation for cyclotron production of 61Cu as a PET imaging

The effects of nuclear level density model and alpha optical model potential to the excitation functions of novel therapeutic radionuclides

In this study, the theoretical cross sections of 209Bi(α,2n)211At, 65Cu(α,n)68Ga, 100Ru(α,n)103Pd, and 121Sb(α,n)124I are calculated using TALYS 1.96, incorporating the effects of the alpha optical model potential and nuclear level density models. The validation process involves comparing the calculated cross sections with experimental data and utilizing statistical deviation factors. This comparison allows us to determine the optimal combination of nuclear model parameters for each reaction. The result shows that theoretical calculations which utilized semi microscopic level density models and alpha OMP managed to describe the excitation functions close to the experimental data. The comparison of nuclear model calculations with experimental data plays a crucial role in ensuring the reliability of the data, making it an essential aspect of modern evaluation procedures.

Calculation of double differential neutron cross-sections of 56Fe and 90Zr isotopes

This study is concerned with the calculations of double differential neutron cross-sections of the structural fusion materials of ⁵⁶Fe and ⁹⁰Zr isotopes that are bombarded with protons. Calculations were performed using the level density models of the TALYS 1.95 code and PHITS 3.22 Monte Carlo code. Constant Temperature Fermi Gas, Back Shifted Fermi Gas, and Generalized Super Fluid Models were employed for level density models. Calculations were performed at 22.2 MeV proton energies. Calculations were compared with the experimental data taken from Experimental Nuclear Reaction Data (EXFOR). In conclusion, the results showed that the level density model results of TALYS 1.95 codes for the double differential neutron cross-sections of ⁵⁶Fe and ⁹⁰Zr isotopes are consistent with experimental data. On the other hand, PHITS 3.22 results gave lower cross-section values than experimental data at 120 and 150°.

Evaluation of nuclear reaction cross sections for optimization of production of the non-standard positron emitting radionuclide 90Nb using proton induced reactions on Zr target

Niobium-90 radionuclide is one of the promising candidates for the positron emission tomography (PET) technique. In this study, ⁹⁰Nb excitation functions via ⁹⁰Zr(p,n) and ^natZr(p,xn) reactions were computed using the TALYS-1.95 code based on phenomenological and microscopic level density models. The MCNPX simulation code was used for each case. Moreover, the target thicknesses were obtained using the SRIM-2013 code and the theoretical and simulation-based production yields of the ⁹⁰Nb were evaluated. The experimental production yield amounts of about 72.68 and 126.7 (both in MBq/μAh) for ⁹⁰Zr(p,n) and ^natZr(p,xn) reactions in the corresponding optimal energy windows were attained by our experiments respectively.

Estimations of giant dipole resonance parameters using artificial neural network

In this study; Giant Dipole Resonance (GDR) parameters of the spherical nucleus have been estimated by using artificial neural network (ANN) algorithms. The ANN training has been carried out with the Levenberg-Marquardt feed-forward algorithm in order to provide fast convergence and stability in ANN training and experimental data, taken from Reference Input Parameter Library (RIPL). R values of the system have been found as 0.99636, 0.94649, and 0.98318 for resonance energy, full width half maximum, and resonance cross-section, respectively. Obtained results have been compared with the GDR parameters which are taken from the literature. To validate our findings, newly acquired GDR parameters were then replaced with the existing GDR parameters in the TALYS 1.95 code and ^142-146Nd(γ,n)^141-145Nd reaction cross-sections have been calculated and compared with the experimental data taken from the literature. As a result of the study, it has been shown that ANN algorithms can be used to calculate the GDR parameters in the absence of the experimental data.

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.

Investigations of proton and deuteron induced nuclear reactions on natural and enriched Titanium, Calcium and Vanadium targets, with special reference to the production of 47Sc

⁴⁷Sc could be used in SPECT imaging and also suitable for targeted therapy of small tumors. The excitation functions for the production of ⁴⁷Sc and accompanying impurities via proton and deuteron bombardment of Calcium, Titanium and Vanadium targets were evaluated by three nuclear codes, ALICE, TALYS and EMPIRE. Therefrom, integral yields of ⁴⁷Sc and also ^46gSc as a main impurity were calculated. The various production routes of ⁴⁷Sc were compared together. The results consistency with available experimental data was checked for each reaction. Based on the results, the ⁴⁶Ca(d,n)⁴⁷Sc reaction can leads to the high purity ⁴⁷Sc with the moderate yield.

64Cu, a powerful positron emitter for immunoimaging and theranostic: Production via natZnO and natZnO-NPs

⁶⁴Cu is one of the most beneficial radionuclide that can be used as a theranostic agent in Positron Emission Tomography (PET) imaging. In this current work, ⁶⁴Cu was produced with zinc oxide nanoparticles (^natZnONPs) and zinc oxide powder (^natZnO) via the ⁶⁴Zn(n,p)⁶⁴Cu reaction in Tehran Research Reactor (TRR) and the activity values were compared with each other. The theoretical activity of ⁶⁴Cu also was calculated with MCNPX-2.6 and the cross sections of this reaction were calculated by using TALYS-1.8, EMPIRE-3.2.2 and ALICE/ASH nuclear codes and were compared with experimental values. Transmission Electronic Microscopy (TEM), Scanning Electronic Microscopy (SEM) and X-Ray Diffraction (XRD) analysis were used for samples characterizations. From these results, it's concluded that ⁶⁴Cu activity value with nanoscale target was achieved more than the bulk state target and had a good adaptation with the MCNPX result.

An overview of (124)I production at a medical cyclotron by ALICE/ASH, EMPIRE-3.2.2 and TALYS-1.6 codes

Excitation functions of proton, deuteron and alpha induced nuclear reactions on enriched tellurium and antimony isotopes and also natural antimony were calculated by ALICE/ASH, EMPIRE-3.2.2 and TALYS-1.6 nuclear codes. Therefrom, the production yield of (124)I nuclide and its formed impurities were calculated by using the evaluation results. The calculated cross sections were compared with available experimental values in literatures. According to results, (124)Te(p,n)(124)I reaction is the method of choice due to formation of higher amount of (124)I nuclide and low levels of (125)I as an major concern in (124)I production.