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.

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.

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

Excitation functions based on level density were calculated for proton-induced on yttrium-89 using the TALYS-1.8 code. Hence, production cross-section of the 89Y(p,x)86,88,89gZr, 86g,87g,88gY, 85gSr, and 84gRb were computed up to 50 MeV. In this study, the constant temperature model alongside the Fermi Gas model (CGCM) was employed as a default model. For this reason, the a-parameter as an essential parameter in the Fermi Gas formula was modified to obtain the best result. Besides, the Back-shifted Fermi Gas Model (BSFGM) and the Generalized Superfluid Model (GSM) are presented to the deliberation. The outcomes of cross-sections were compared with the experimental data approaching regarding desired consequences.

Modeling and experimental data of zirconium-89 production yield.

The radionuclide zirconium-89 can be employed for the positron emission tomography (PET). In this study 89Zr excitation function via 89Y(p,n)89Zr reaction was calculated by the TALYS-1.8 code based on microscopic level density model. The formation of 89Zr was simulated using the Monte Carlo simulation code MCNPX to calculate the integral yield in the 89Y target body for threshold up to 40MeV incident-proton energy. The target thickness was based on calculation of the stopping power using the SRIM-2013 code matched to any incident-proton energy. The production yield of the 89Zr simulated with the Monte Carlo method for the 89Y(p,n)89Zr, 89Y(d,2n)89Zr, natSr(α,xn)89Zr and natZr(p,pxn)89Zr reactions and the results were in good agreement with published experimental results for the optimum energy range. An experimental yield of 53.1MB/µA for the 15MeV proton-induced on Y2O3 powder as a disk-target obtained for 1h irradiation at the AMIRS cyclotron.

Utilization of GEANT to calculation of production yield for 89Zr by charge particles interaction on 89Y, natZr and natSr.

The 89Zr, is one of the radionuclide with near-ideal properties for PET due to its suitable half-life and decay properties. The cross-section of 89Zr via 89Y(p,n)89Zr, 89Y(d,2n)89Zr, natSr(α,xn)89Zr and natZr(p,pxn)89Zr, were calculated by the TALYS-1.8 code to predict the optimum range of charge particle energy. The Monte Carlo code GEANT4 was used to simulate the formation of 89Zr in the target body. The simulated 89Zr yield was in good agreement with published experimental results in the optimum energy range. According to the calculations, the 89Y(p,n)89Zr was superior to the other reactions useful to medical application.

Investigative for no-carrier-added 87m,gY production by the proton-induced on 89Y.

The radioisotope 87Y is one of the candidates for the SPECT and 87Y/87mSr generator due to its suitable half-life and decay properties. The proton-induced on the 89Y target can be used for the production of 87Y. The present perusal calculated the excitation function for the both 89Y(p,x)87m,gY direct reaction and decay of 87Zr via 89Y(p,3n)87Zr → 87mY → 87gY indirect reaction using the TALYS-1.8 code. To simulation the production of 87m,gY nuclide, the target thickness was designed based on the stopping power calculation by the SRIM-2013 code. The Monte Carlo code GEANT4 was used to simulate the transport of protons through the irradiation assembly. Then, the cumulative integral yield of the 87m,gY has been calculated directly after the decay of 87Zr radionuclide entirely. These results were in good agreement with the theoretical and reported experimental data. Eventually, the integral yield of the 87m,gY was calculated by the indirect method from 87Zr decay after separation the zirconium. This work provides the basis for theoretical appraisement of the use of no-carrier-added 87Y as radiopharmaceutical for the purpose of medical applications.