Neutron radiative capture cross section for sodium with covariance analysis

Gandhi, A.; Sharma, Aman; Pachuau, Rebecca; Lalremruata, B.; Mehta, Mayur; Patil, P. N.; Suryanarayana, S. V.; Danu, L. S.; Nayak, B. K.; Kumar, Ajay

doi:10.1140/epja/s10050-020-00322-6

Cited by 42 publications

(11 citation statements)

References 48 publications

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“…A spread in the neutron spectrum of can be observed because of the energy degradation of protons in the target. The average neutron energy of the neutron group was obtained by using the following equation [16,17]:…”

Section: Bementioning

confidence: 99%

“…The standard data library for neutron monitor reaction cross-section IRDFF-II [20] was used for reference monitor reaction cross-section . As the neutrons generated by the reaction are not monoenergetic but rather have an energy spread, the neutron flux energy spectrum produced by the EPEN [13] code was used to fold the point-wise monitor crosssection in the IRDFF-II library ( ) using the following equation [16]: [7] data library and recommended values from the IRDFF-II library [20].…”

Section: E Cross-sections For Reference Monitor Reactions and Their C...mentioning

confidence: 99%

“…Therefore, the standard efficiency calibration source was also placed at a distance of 6.0 mm from the detector. This, in turn, produced the coincidence summing effect [16]. The Monte Carlo simulation code EFFTRAN [19] was used to compute the correction factor , and corrections to the measured detector efficiency were made.…”

mentioning

confidence: 99%

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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: Bementioning

confidence: 99%

Section: E Cross-sections For Reference Monitor Reactions and Their C...mentioning

confidence: 99%

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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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“…4.1.3 of Ref. [30]. In the calculation of the timing factor, we considered the uncertainty in the residues' decay constants because the uncertainties in the , , and timings were negligible.…”

Section: Uncertainty Analysis: a Salmentioning

confidence: 99%

“…A similar procedure was used in literature [23,[30][31][32]. Table 8 lists the measured reaction cross sections, their total uncertainties, and their correlation matrix.…”

Section: Uncertainty Analysis: a Salmentioning

confidence: 99%

Measurement of (n,α) and (n,2n) reaction cross sections at a neutron energy of 14.92 ± 0.02 MeV for potassium and copper with uncertainty propagation *

et al. 2022

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Experimentally measured neutron activation cross sections are presented for the (n,α) , (n,α) , and (n,2n) reactions with detailed uncertainty propagation. The neutron cross sections were measured at an incident energy of 14.92 ± 0.02 MeV, and the neutrons were based on the t(d,n)α fusion reaction. The (n,α) reaction was used as a reference reaction for the normalization of the neutron flux. The pre-calibrated lead-shielded HPGe detector was used to detect the residues' γ-ray spectra. The data from the measured cross sections are compared to the previously measured cross sections from the EXFOR database, theoretically calculated cross sections using the TALYS and EMPIRE codes, and evaluated nuclear data.

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Landau Quantization for Relativistic Vector Bosons in a Gödel-Type Geometric Background

Doğan

2022

Few-Body Syst

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Neutron radiative capture cross section for sodium with covariance analysis

Cited by 42 publications

References 48 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 (n,α) and (n,2n) reaction cross sections at a neutron energy of 14.92 ± 0.02 MeV for potassium and copper with uncertainty propagation *

Landau Quantization for Relativistic Vector Bosons in a Gödel-Type Geometric Background

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Neutron radiative capture cross section for sodium with covariance analysis

Cited by 42 publications

References 48 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 (n,α) and (n,2n) reaction cross sections at a neutron energy of 14.92 ± 0.02 MeV for potassium and copper with uncertainty propagation *

Landau Quantization for Relativistic Vector Bosons in a Gödel-Type Geometric Background

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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*