Evaluation of nuclear reaction cross section data of proton and deuteron induced reactions on 75As, with particular emphasis on the production of 73Se

75Se (T1/2 = 120 d), 73gSe (T1/2 = 7.1 h) and 72Se (T1/2 = 8.4 d) are important radioisotopes of selenium, being used in tracer studies, PET investigations and as a generator parent, respectively. Cross section data for the formation of those radionuclides in proton and deuteron induced reactions on 75As were critically analyzed up to about 70 MeV. A well-developed evaluation methodology was applied to generate the statistically fitted cross sections, based on the critically analyzed literature experimental data and the theoretical cross section values of three nuclear model codes ALICE-IPPE, TAYLS 1.9, and EMPIRE 3.2. Using the fitted cross sections the integral yield of each radionuclide was calculated. For the estimation of impurities, the integral yield of each radionuclide was compared with the yields of the other two radionuclides over a given energy region, and therefrom the energy range was suggested for the high purity production of each of the radionuclides 75Se, 73Se and 72Se. For production of the very important non-standard positron emitter 73Se via the 75As(p,3n)73Se reaction, the optimum energy range was deduced to be E p = 40 → 30 MeV, with a thick target yield of 1441 MBq/μAh and the 72,75Se impurity level of <0.1%.

Production calculation of medical 67Ga, 111In, 117mSn, 131,125,123I, 133Xe, 153Sm, 159Gd, 188Re and 201Tl nuclei used for cancer diagnostics in single photon emission computed tomography via theoretical models

This paper aims to examine the production of diagnostic radioisotopes used in Single Photon Emission Computed Tomography (SPECT) using six different level density models. The cross-section curves and the integral yield of reaction processes were calculated using the TALYS code and X-PMSP program for the level density models in the energy region of 1–100 MeV with the constant particle beam current of 1 [Formula: see text]A and irradiation time of 1 h. The results have been compared with the experimental and the data recommended in the literature. To overcome the lack of experimental and theoretical yield data of reaction processes, the integral yield results obtained by the cross-sections and mass stopping powers in the production of radioisotopes contributed new insights to the nuclear data in the literature. Based on the obtained data, the calculated results have been discussed, and the obtained new data, appropriate energy regions and reaction processes for the production of diagnostic radioisotopes have also been recommended.

Investigation of production of samarium-151 and europium-152,154,155 via particle accelerator

This work aimed to investigate the production of [Formula: see text]Sm and [Formula: see text]Eu on natural Nd and Sm targets via particle accelerator because these radionuclides have the potential for use in nuclear battery technology such as betavoltaic batteries and radioisotope thermoelectric generators. Therefore, this work estimated cross-section curves for proton, deuteron, triton, helium-3, and alpha particles induced reactions in the energy range [Formula: see text]. The activities and products of yield were simulated for all reaction processes under selected conditions, the particle beam current of 1 mA and the irradiation time of 24 h. Moreover, to understand the formations of [Formula: see text] and [Formula: see text]Eu in the reaction processes, the appropriate energy region of the reactions by calculating the integral yield curves were determined. Based on the obtained results, determination of suitable targets, energy regions, and reaction processes were discussed by this work.

Investigation of the production of cobalt-60 via particle accelerator

The production process of cobalt-60 was simulated by a particle accelerator in the energy range of 5 to 100 MeV, particle beam current of 1 mA, and irradiation time of 1 hour to perform yield, activity of reaction, and integral yield for charged particle-induced reactions. Based on nuclear reaction processes, the obtained results in the production process of cobalt-60 were also discussed in detail to determine appropriate target material, optimum energy ranges, and suitable reactions.

Comparison of nuclear data of 64Cu production using an accelerator by TALYS 1.0 code

The extensive use of 64Cu (T1/2 = 12.7 h) as a positron and electron emitter radioisotope in recent years has ensured its potential to serve a dual role in the development of molecular agents in PET and radioimmunotheraphy drugs in oncology. The TALYS 1.0 code was used to calculate excitation functions for induced proton, deuteron and alfa-particles on 64Zn, 66Zn, 67Zn, 68Zn, 70Zn, 62Ni, and 64Ni up to 50 MeV. According to the data acquired by the TALYS 1.0 code, thick-target integral yield of the induced charged particles on the enriched targets was achieved.