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

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.