scholarly journals Reaction Cross–Section Calculations for the Structural Reactor Materials 58,60,61,62,64Ni with Different Level Density Models

2016 ◽  
Vol 37 (0) ◽  
pp. 151
Author(s):  
Veli ÇAPALI ◽  
Mert ŞEKERCİ ◽  
Hasan ÖZDOĞAN ◽  
Abdullah KAPLAN
2015 ◽  
Vol 78 (1) ◽  
pp. 53-64 ◽  
Author(s):  
A. Kaplan ◽  
İ. H. Sarpün ◽  
A. Aydın ◽  
E. Tel ◽  
V. Çapalı ◽  
...  

2015 ◽  
Vol 78 (01) ◽  
pp. 57-68
Author(s):  
A. Kaplan ◽  
İ. H. Sarpün ◽  
A. Aydın ◽  
E. Tel ◽  
V. Çapalı ◽  
...  

1999 ◽  
Vol 112 (7) ◽  
pp. 743-760 ◽  
Author(s):  
V. P. Lunev ◽  
Yu. N. Shubin ◽  
C. Grandi ◽  
B. Poli ◽  
A. Ventura

2022 ◽  
Author(s):  
RATANKUMAR SINGH ◽  
N.L. Singh ◽  
Rakesh Chauhan ◽  
Mayur Mehta ◽  
Saraswatula suryanarayan ◽  
...  

Abstract The cross sections of the 121Sb(n,2n) 120Sbm and 123Sb(n,2n) 122Sb reactions were measured at 12.50, 15.79 and 18.87 MeV neutron energies relative to the standard 27Al(n,α) 24Na monitor reaction using neutron activation and offline γ-ray spectrometry technique. Irradiations of the samples were performed at the BARC-TIFR Pelletron Linac Facility, Mumbai, India. The quasi-monoenergetic neutron was generated via the 7Li(p,n) reaction. Statistical model calculations were performed by nuclear reaction codes TALYS (ver. 1.9) and EMPIRE (ver. 3.2.2) using various input parameters and nuclear level density models. The cross sections of the ground and the isomeric state as well as the isomeric cross section ratio were studied theoretically from reaction threshold to 26 MeV energies. The effect of pre-equilibrium emission is also discussed in detail using different theoretical models. The present measured cross section were discussed and compared with reported experimental data and evaluation data of the JEFF-3.3, ENDF/B-VIII.0, JENDL/AD-2017 and TENDL-2019 libraries. A detailed analysis of the uncertainties in the measured cross section data was performed using the covariance analysis method. Furthermore, a systematic study of the (n,2n) reaction cross section for 121Sb and 123Sb isotopes were also performed within 14-15 MeV neutron energies using various systematic formulae. This work helps to overcome discrepancies in Sb data and illustrate a better understanding of pre-equilibrium emission in (n,2n) reaction channel.


2019 ◽  
Vol 34 (26) ◽  
pp. 1950210 ◽  
Author(s):  
İsmail Hakki Sarpün ◽  
Hasan Özdoğan ◽  
Kemal Taşdöven ◽  
Hüseyin Ali Yalim ◽  
Abdullah Kaplan

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.


Kerntechnik ◽  
2021 ◽  
Vol 86 (6) ◽  
pp. 411-418
Author(s):  
Y. Kavun ◽  
R. Makwana

Abstract 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.


2020 ◽  
Vol 15 ◽  
pp. 97
Author(s):  
N. Patronis ◽  
C. T. Papadopoulos ◽  
S. Galanopoulos ◽  
M. Kokkoris ◽  
G. Perdikakis ◽  
...  

The 191Ir(n,2n)190Ir cross section was measured by using of the activation technique at four neutron energies in the range 10.0-11.3 MeV. The quasimonoenergetic neutron beam was produced via the 2H(d,n)3He reaction at the 5.5 MV Tandem Van de Graaff accelerator of NCSR ”Demokritos”. After the irradiations the induced activity of the samples was measured through a 56% relative efficiency HPGe detector. The cross section for the population of the second high spin (11−) isomeric state was measured along with the sum of the reaction cross section populating both the ground (4−) and the first isomeric state (1−). The experimental data will be combared to theoretical calculations in order to deduce information for the spin dependence of the level density parameters.


2019 ◽  
Vol 108 (1) ◽  
pp. 11-17
Author(s):  
Mert Şekerci ◽  
Hasan Özdoğan ◽  
Abdullah Kaplan

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.


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