Effects of some level density models and γ-ray strength functions on production cross-section calculations of 16,18O and 24,26Mg radioisotopes

Oxygen and magnesium isotopes can be used in nuclear reactor materials as cooling, shielding, coating, electronics etc. They can also occur through nuclear reactions during the reactor operation. The exposure of high energy gamma can change the material and its properties, and hence its objective of selection may not remain satisfied. Thus, it is required to study the cross section of different reactions on nuclear reactor materials to understand their sustainability for the properties, for which they are chosen. In the scope of this study, theoretically, different level density model calculations and γ-ray strength functions have been performed for (γ, p) reaction for 16,18O and 24,26Mg nuclei using TALYS 1.9 and EMPI˙RE 3.2.2 codes. Also, semi empirical (γ, p) formula by Tel et al., have been calculated and compared with all results. The effect of different level density models defined in these codes on gamma strength has been studied. Finally, the consistency of these obtained data with EXFOR data have been investigated.

Production cross–section and reaction yield calculations for 123-126I isotopes on 123Sb(α,xn) reactions

Most of the radioisotopes used in the medical fields, like examination and treatment studies, were produced by employing nuclear reactions. Within the process of a nuclear reaction, one of the most important parameters is the cross-section data, which help reveal the reaction phenomenon's mechanisms. The main intention of this study is to investigate the efficiencies of producing iodine isotopes via 123Sb(α,xn) reactions. For this, optical and level density models of TALYS 1.8 code have been used. Production cross-section, the alpha beam energy, reaction yields, and total activation of radioisotopes have been computed. It has been figured out that a 45 MeV cyclotron could be enough for producing 123-126I radioisotopes with reaction yields of 39.3372, 5.5685, 0.2410, and 0.0796 GBq/mAh, respectively.

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.

An investigation of the effects of level density models and alpha optical model potentials on the cross-section calculations for the production of the radionuclides 62Cu, 67Ga, 86Y and 89Zr via some alpha induced reactions

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.

Level density model effects on the production cross-section calculations of some medical isotopes via (α, xn) reactions where x = 1–3

Level density models have an undeniable importance for a better perception on the nature of nuclear reactions, which influences our life via various ways. Many novel and advanced medical application use radioisotopes, which are produced with nuclear reactions. By considering the connection between the level density models and the importance of theoretical calculations for the production routes of medically important isotopes, this study is performed to investigate the level density model effects on the production cross-section calculations of [Formula: see text]Zn, [Formula: see text]Ga, [Formula: see text]Kr, [Formula: see text]Pd, [Formula: see text]In, [Formula: see text]I and [Formula: see text]At radioisotopes via some alpha particle induced and neutron emitting reactions. For theoretical calculations; frequently used computation tools, such as TALYS and EMPIRE codes, are applied. Obtained theoretical results are then compared with the experimental data, taken from Experimental Nuclear Reaction Data (EXFOR) library. For a better interpretation of the results, a mean weighted deviation calculation for each investigated reaction is performed in addition to a visual comparison of the graphical representations of the outcomes.

Production Cross–Section Calculations of 62Cu via Charged Particles Induced Reactions

The utilization of radioisotopes has been increasing proportionally with the scientific and industrial developments. Among many known and used examples of them, 62Cu has a wide usage due to its suitability for many specific requirements such as in medical applications. By considering the importance of radioisotopes and especially 62Cu, in this study, the theoretical calculations of cross–section values for 62Cu via 59Co(α,n)62Cu, 61Ni(d,n)62Cu, 62Ni(d,2n)62Cu and 62Ni(p,n)62Cu reactions were carried out by employing three phenomenological level density models via TALYS 1.9 code. Obtained results were compared with the available experimental data from Experimental Nuclear Reaction Data (EXFOR) Library by graphically and mathematically.

An investigation of effects of level density models and gamma ray strength functions on cross-section calculations for the production of 90Y, 153Sm, 169Er, 177Lu and 186Re therapeutic radioisotopes via (n,γ) reactions

One of the methods used to treat different cancer diseases is the employment of therapeutic radioisotopes. Therefore, many clinical, theoretical and experimental studies are being carried out on those radioisotopes. In this study, the effects of level density models and gamma ray strength functions on the theoretical production cross-section calculations for the therapeutic radioisotopes 90Y, 153Sm, 169Er, 177Lu and 186Re in the (n,γ) route have been investigated. TALYS 1.9 code has been used by employing different level density models and gamma ray strength functions. The theoretically obtained data were compared with the experimental data taken from the literature. The results are presented graphically for better interpretation.

Theoretical photoneutron cross-section calculations on Osmium isotopes by Talys and Empire codes

In this study, the level density parameter and the gamma ray strength function effects on photoneutron reaction cross-section calculations for Osmium isotopes were investigated by employing available level density models and gamma ray strength functions within Talys v1.8 and Empire v3.1 nuclear codes. A relative variance analysis was done to determine the best gamma ray strength function. Then, the effect of level density models for the photoneutron reactions was investigated by using the best gamma ray strength function. The results were compared with each other and also with the experimental data taken from the literature.

The (n,γ) reaction productions of 35S, 42Ar, 45Ca, 63Ni, 85Kr, 89Sr, 113mCd, 121m,123Sn, 147Pm, 151Sm, 152,154,155Eu, 170,171Tm, 185,188W, 194Os, 204Tl, 210Po, 227Ac, 242,244Cm radioisotopes for using in nuclear battery via phenomenological and microscopic level density models

Aims of this work are: (i) Investigation of the production of some radioisotopes that could be used in nuclear battery technology with neutron-induced reaction processes, (ii) Estimation of the cross-section curves of [Formula: see text] reactions for astrophysical processes in the energy region between 1[Formula: see text]eV and 1[Formula: see text]MeV, (iii) Determination of suitable level density models for the [Formula: see text] reaction processes. Additionally, the obtained results were compared with the experimental data and recommended data. Based on the calculated results, to eliminate lack of nuclear data in the literature, we recommend new experiments for some reaction processes to be performed by the experimenters. Moreover, for the [Formula: see text] reaction processes, suitable level density models were proposed.