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

2019 ◽  
Vol 28 (08) ◽  
pp. 1950057 ◽  
Author(s):  
Ozan Artun
Keyword(s):  
Cross Section ◽  
Level Density ◽  
Nuclear Data ◽  
Microscopic Level ◽  
Level Density Models ◽  
Battery Technology ◽  
Reaction Processes ◽  
Nuclear Battery ◽  
Induced Reaction

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.

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

2019 ◽  
Vol 34 (20) ◽  
pp. 1950154 ◽  
Author(s):  
Ozan Artun
Keyword(s):  
Irradiation Time ◽  
Particle Beam ◽  
Beam Current ◽  
Alpha Particles ◽  
Particle Accelerator ◽  
Integral Yield ◽  
Battery Technology ◽  
Reaction Processes ◽  
Nuclear Battery

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.

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

2020 ◽  
Vol 108 (6) ◽  
pp. 459-467
Author(s):  
Mert Şekerci
Keyword(s):  
Nuclear Reaction ◽  
Cross Section ◽  
Optical Model ◽  
Level Density ◽  
Model Potentials ◽  
Consistent Model ◽  
Level Density Models ◽  
Chi Squared ◽  
The Cross ◽  
Reaction Processes

AbstractTheoretical 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.

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

2019 ◽  
Vol 108 (1) ◽  
pp. 11-17
Author(s):  
Mert Şekerci ◽  
Hasan Özdoğan ◽  
Abdullah Kaplan
Keyword(s):  
Experimental Data ◽  
Cross Section ◽  
Production Cross Section ◽  
Gamma Ray ◽  
Production Cross ◽  
Level Density ◽  
Experimental Studies ◽  
Level Density Models ◽  
Strength Functions ◽  
Cancer Diseases

Abstract 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.

scholarly journals Impact of the cross section library on 93mNb activity in VVER-1000 reactor dosimetry

2020 ◽  
Vol 225 ◽  
pp. 03009
Author(s):  
P. Haroková ◽  
M. Lovecký
Keyword(s):  
Cross Section ◽  
Neutron Transport ◽  
Nuclear Data ◽  
Nuclear Data Library ◽  
The Cross ◽  
Materials Used ◽  
The Impact ◽  
Data Library ◽  
Reactor Dosimetry

One of the objectives of reactor dosimetry is determination of activity of irradiated dosimeters, which are placed on reactor pressure vessel surface, and calculation of neutron flux in their position. The uncertainty of calculation depends mainly on the choice of nuclear data library, especially cross section used for neutron transport and cross section used as the response function for neutron activation. Nowadays, number of libraries already exists and can be still used in some applications. In addition, new nuclear data library was recently released. In this paper, we have investigated the impact of the cross section libraries on activity of niobium, one of the popular materials used as neutron fluence monitor. For this purpose, a MCNP6 model of VVER-1000 was made and we have compared the results between 14 commonly used cross section libraries. A possibility of using IRDFF library in activation calculations was also considered. The results show good agreement between the new libraries, with the exception of the most recent ENDF/B-VIII.0, which should be further validated.

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

2020 ◽  
Vol 35 (24) ◽  
pp. 2050202
Author(s):  
Mert Şekerci ◽  
Hasan Özdoğan ◽  
Abdullah Kaplan
Keyword(s):  
Cross Section ◽  
Production Cross Section ◽  
Nuclear Reactions ◽  
Theoretical Calculations ◽  
Production Cross ◽  
Level Density ◽  
Medical Application ◽  
Density Model ◽  
Level Density Models ◽  
Theoretical Results

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.

Fission Cross Section Calculation Using TALYS Based on Two Different Level Density Models

2010 ◽  
Author(s):  
R. Kurniadi ◽  
Yudha S. Perkasa ◽  
K. Basar ◽  
A. Waris ◽  
Zaki Su’ud ◽  
...  
Keyword(s):  
Cross Section ◽  
Level Density ◽  
Fission Cross Section ◽  
Level Density Models

(γ, 2n)-Reaction cross-section calculations of several even-even lanthanide nuclei using different level density models

2015 ◽  
Vol 78 (1) ◽  
pp. 53-64 ◽  
Author(s):  
A. Kaplan ◽  
İ. H. Sarpün ◽  
A. Aydın ◽  
E. Tel ◽  
V. Çapalı ◽  
...  
Keyword(s):  
Cross Section ◽  
Reaction Cross Section ◽  
Level Density ◽  
Reaction Cross ◽  
Level Density Models
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