Measurements of neutron capture cross sections on 
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 at 0.96 and 1.69 MeV

Punte, L. R. M.; Lalremruata, B.; Otuka, Naohiko; Suryanarayana, S. V.; Iwamoto, Yosuke; Pachuau, Rebecca; Satheesh, B.; Thanga, H. H.; Danu, L. S.; Desai, Vimal; Hlondo, L. R.; Kailas, S.; Ganesan, S.; Nayak, B. K.; Saxena, A.

doi:10.1103/physrevc.95.024619

Cited by 19 publications

(5 citation statements)

References 25 publications

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“…However, in the current proton energy range, the contribution of the reaction channel to the neutron yield was negligible. However, the contribution of the channel to the neutron yield was maximum and was approximately 90%, followed by that of the channel, which was less than 10% [14,15]. With the EPEN code, it is possible to acquire the individual and neutron energy distribution as well as the total neutron energy distribution from both groups for a specified incident proton energy.…”

Section: A Neutron Productionmentioning

confidence: 99%

Investigation of ⁵⁸Ni (n, p)⁵⁸Co reaction cross-section with covariance analysis*

Hingu,

Mukherjee,

Parashari

et al. 2024

Chinese Phys. C

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The excitation function of the $\rm {}^{58}Ni ( n, p ){}^{58}Co$ reaction is measured by using the well-established neutron activation technique and $\gamma$-ray spectroscopy. Neutrons in the energy range of 1.7 to 2.7 $\rm MeV$ were generated using the $\rm ^{7}Li(p, n)$ reaction. The neutron flux was measured by using the standard $\rm {}^{115}In ( n, n^{'} ){}^{115m}In$ monitor reaction. The results of neutron spectrum averaged cross-section of $\rm {}^{58}Ni ( n, p ){}^{58}Co$ reactions are compared with existing cross-section data available in the EXFOR data library as well as with various evaluated data libraries like ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0 and CENDL-3.2. Theoretical calculations were performed using the nuclear reaction code TALYS. Various nuclear level density (NLD) models were tested and compared with the present findings. Realistic NLDs are also obtained through the spectral distribution method (SDM). The cross-section results are reported along with the absolute errors by investigating uncertainty propagation, using the covariance technique. The corrections for $\gamma$-ray true coincidence summing, low-energy background neutrons and $\gamma$-ray self attenuation are performed. The experimental cross-section obtained in the present study is consistent with previously published experimental data, evaluated libraries and theoretical calculations carried out using the TALYS code.

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Section: A Neutron Productionmentioning

confidence: 99%

Investigation of ⁵⁸Ni (n, p)⁵⁸Co reaction cross-section with covariance analysis*

Hingu,

Mukherjee,

Parashari

et al. 2024

Chinese Phys. C

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“…In order to correct the coincidence-summing effect, the correction factor was calculated using the Monte Carlo simulation code EFFTRAN [21,22]. Since the activated sample has a finite area, the efficiency calculated for the point-source geometry ( ) was transferred to the efficiency for the sample geometry (ε) using the EFFTRAN code.…”

Section: B Sample Details N N ′mentioning

confidence: 99%

Measurement of neutron capture cross section on ⁷¹Ga at 2.15 and 3.19 MeV and uncertainty propagation and covariance analysis*

et al. 2023

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The cross section values of the 71Ga(n,γ)72Ga reaction have been measured which are 9.14 ± 0.81 mb and 5.74 ± 0.50 mb at 2.15 and 3.19 MeV, respectively. The detail uncertainty propagation and covariance analysis are also given. The 7Li(p,n)7Be reaction was used to generate the neutrons and the neutron flux was normalised using the 115In(n,n’ )115Inm monitor reaction. The measured cross sectiondata are compared with the data available in the EXFOR database and with those of nuclear reaction model codes EMPIRE-3.2 and TALYS-1.95 and also with the evaluated nuclear data from ENDF/B-VIII.0 and JEFF-3.1/A. The comparison shows that our result at 3.19 MeV is in good agreement with those of EMPIRE-3.2 and JEFF-3.1/A. Since there are no other measurements available at 3.19 MeV, our data could not be compared with literature data at 3.19 MeV but it is consistent with the cross section values available at 2.98 ± 0.26 and 3.0 ± 0.1 MeV and our result at 2.15 MeV is slightly higher than the literature value available in EXFOR, evaluated value and theoretical predicted result.

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“…The calculated efficiency value for sample source geometry ( ) and point source geometry ( p ) placed at 62.5 mm from the detector absorber are given in Table III with the correction factor (K C ). To calculate the efficiency of a particular γ-ray of the product radionuclide, we have used equation 2 which is a fitting function of interpolating the point-wise efficiencies (E γ ) of the γ-ray energy (E γ ) of the standard source 152 Eu [17,20].…”

Section: E F F I C I E N C Y P O I N T F I T T I N G C U R V Ementioning

confidence: 99%

“…The efficiency of the HPGe detector for different gamma energies was calculated by using a 152 Eu point source which has initial activity A 0 = 3.908×10 a half-life of T 1/2 = 13.517 ± 0.009 years. The following equation is used to calculate the detection efficiency of the HPGe detector for a source detector distance of 62.5 mm [17]:…”

Section: Introductionmentioning

confidence: 99%

Measurement of alpha-induced reaction cross-sections on $^{nat}$Zn with detailed covariance analysis

Choudhary¹,

Gandhi²,

Sharma³

et al. 2022

Preprint

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The production cross-section of 68 Ge, 69 Ge, 65 Zn and 67 Ga radioisotopes from alpha induced nuclear reaction with nat Zn have been measured using stacked foil activation technique followed by the off-line γ-ray spectroscopy in the incident alpha energy range 14.47-37 MeV. In this study we have presented cross-sections for nat Zn(α,x) 68 Ge, nat Zn(α,x) 69 Ge, nat Zn(α,x) 65 Zn and nat Zn(α,x) 67 Ga reactions. The obtained nuclear reaction cross-sections are compared with previous experimental data available in the EXFOR data library and theoretical results, calculated using TALYS nuclear reaction code. We have also performed the detailed uncertainty analysis for these nuclear reactions and their respective covariance metrics are presented. Since α-induced reactions are important in astrophysics, nuclear medicine, and improving the nuclear reaction codes so needful corrections related to the coincidence summing factor and the geometric factor have been considered during the data analysis in the present study.

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Measurements of neutron capture cross sections on Zn70 at 0.96 and 1.69 MeV

Cited by 19 publications

References 25 publications

Investigation of ⁵⁸Ni (n, p)⁵⁸Co reaction cross-section with covariance analysis*

Investigation of ⁵⁸Ni (n, p)⁵⁸Co reaction cross-section with covariance analysis*

Measurement of neutron capture cross section on ⁷¹Ga at 2.15 and 3.19 MeV and uncertainty propagation and covariance analysis*

Measurement of alpha-induced reaction cross-sections on $^{nat}$Zn with detailed covariance analysis

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Measurements of neutron capture cross sections on Zn70 at 0.96 and 1.69 MeV

Cited by 19 publications

References 25 publications

Investigation of 58Ni (n, p)58Co reaction cross-section with covariance analysis*

Investigation of 58Ni (n, p)58Co reaction cross-section with covariance analysis*

Measurement of neutron capture cross section on 71Ga at 2.15 and 3.19 MeV and uncertainty propagation and covariance analysis*

Measurement of alpha-induced reaction cross-sections on $^{nat}$Zn with detailed covariance analysis

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Investigation of ⁵⁸Ni (n, p)⁵⁸Co reaction cross-section with covariance analysis*

Investigation of ⁵⁸Ni (n, p)⁵⁸Co reaction cross-section with covariance analysis*

Measurement of neutron capture cross section on ⁷¹Ga at 2.15 and 3.19 MeV and uncertainty propagation and covariance analysis*