Measurement of 
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The cross-sections of the 127I (n, 2n) 126I and 133Cs (n, 2n) 132Cs reactions at the 13.83 ± 0.2, 14.33 ± 0.2 and 14.79 ± 0.2 MeV neutron energies were measured relative to the 93Nb (n, 2n) 92mNb reaction through the activation technique in combination with off-line γ-ray spectrometry. The neutron beam was generated from the T (d, n) 4He reaction using the K-400 neutron generator at the Chinese Academy of Engineering Physics (CAEP). Considering the correlations between different attributes, detailed uncertainty propagation was performed using the covariance analysis, and the cross-sections were reported with their uncertainties and correlation matrix. The uncertainty of the measurement cross-sections ranges from 4.84 to 5.90%, which is lower than the previous experimental data. Furthermore, the theoretical excitation function of 127I (n, 2n) 126I and 133Cs (n, 2n) 132Cs reactions were calculated using the TALYS-1.95 and EMPIRE-3.2.3 codes. Then, experimentally determined cross-sections were analyzed by comparing with the literature data available in the EXFOR database and evaluated nuclear data of the ENDF/B-VIII.0, JEFF-3.3, JENDL-5, BROND-3.1, CENDL-3.2, and TENDL-2019 databases. Compared with the values prior reported in the 13.8-14.8 MeV energies region, the precision of the results obtained in this work is greatly improved. The current experimental results with thorough uncertainties and covariance information are critical for verifying the reliability of the theoretical model and improving the quality of the nuclear database.

Section: A 127 I (N 2n) 126 I Reactionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 96%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Measurement of the (n, 2n) reaction cross-sections of iodine and cesium induced by D-T neutrons with covariance analysis*

Lan,

Niu,

Wei

et al. 2023

“…The main sources of uncertainties during the determination of cross-sections included the following items (where the subscripts Nb/Al and x show the monitored and measured reaction-related terms, respectively): C x,Nb/Al is the γ-ray counting statistics, M x,Nb/Al is the target mass, η x is the target isotopic abundance, I x,Nb/Al refers to the γ-ray intensity, σ Nb/Al is the standard cross-section, ε x,Nb/Al is the efficiency (the calculated covariance and correlation matrix for the HPGe detector efficiency is given in Table 5), and S x,Nb/Al , D x,Nb/Al are the timing factors. The uncertainty within the estimated reaction cross-section was calculated by employing the fractional uncertainty (%) from all the variables listed above [44][45][46][47]. Tables 6-9 were utilized for the propagation of the covariance matrix among the various neutron energies and to illustrate the fractional uncertainties in the different factors responsible for the measured reaction crosssection.…”

Section: B Covariance Analysismentioning

confidence: 99%

New cross-section measurements for the (n, 2n), (n, p), and (n, α) reactions on bromine in the 14 MeV region with detailed uncertainty quantification*

He¹,

Luo²,

Li³

2023

Measurement of the cross-sections of 79Br(n,2n)78Br, 81Br(n,p)81mSe, 81Br(n,α)78As, and 79Br(n,α)76As reactions was carried out at specific neutron energies precisely 13.5±0.2, 14.1±0.2, 14.4±0.2, and 14.8±0.2 MeV relative to the standard 93Nb(n,2n)92mNb and 27Al(n,α)24Na reference reactions using offline γ-ray spectrometry and neutron activation. The monoenergetic neutrons were generated at the China Academy of Engineering Physics, via a 3H(d,n)4He reaction using a K-400 Neutron Generator equipped with a solid 3H-Ti based target. The activity of reaction produce was obtained utilizing a high-purity germanium detector. The cross-sections of the (n,2n), (n,p), and (n,α) reactions on the bromine isotopes were conducted in the 13–15 MeV neutron energy range. The covariance analysis approach was employed for a thorough inspection of any uncertainties within the measured cross-section data. Discussion and comparison of the observed outcome were carried out with previously published data, in particular with the results of the JENDL-4.0, JEFF-3.3, TENDL-2019, and ENDF/B-VIII.0 data libraries, along with the theoretical excitation function curve derived by employed the TALYS-1.95 program. Improved cross-section restrictions for the investigated processes in the 13–15 MeV neutron energy range will be furnished by the current findings, which will help to raise the caliber of the associated databases. Furthermore, the parameters of the pertinent nuclear reaction models can be verified using this data.

“…The (n, p) reaction channel with the Ni isotope leads to the production of the medium-lived radio-isotope Co, which has many medical applications. Its most significant role is as a trace element for the absorption of vitamin B12 in the human body [5].…”

Section: Introductionmentioning

confidence: 99%

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

Hingu,

Mukherjee,

Parashari

et al. 2024

Self Cite

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.