Library of Evaluated Neutron Data Files

Blokhin, A. I.; Ignatyuk, A.V.; Kuz'minov, B.D.; Koshcheev, V. N.; Manokhin, V. N.; Manturov, G. N.; Nikolaev, M.N.

doi:10.1007/978-3-642-58113-7_224

Cited by 10 publications

(10 citation statements)

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“…Those results are shown in Figures 6 and 7. In all plots are results compared with current data from the EXFOR database, simulated cross-sections from Talys 1.4 code, and with some available evaluated data like EAF-2010 [10] or BROND-3.1 [11].…”

Section: Resultsmentioning

confidence: 99%

Cross section determination for TAD materials in quasi mono-energetic neutron spectrum from p(Li) reaction

et al. 2020

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Threshold activation detectors (TAD) are of great importance for a determination of neutron energy spectra and flux density. For different sources, it is necessary to choose the right combination of materials that cover the estimated spectra. Several different materials were irradiated in a quasi-monoenergetic neutron field with 29.1 MeV peak neutrons energy in the CANAM facility. Neutrons were produced in p + Li-7 reaction in a thin target and the foils were situated in the proton beam axis and close geometry to the Li target. The integral number of protons was established from accelerator telemetry and lithium target activation measurements after the experiment. During the experiment, one long irradiation was done for following foils: Al, Au, Bi, Co, Cu, Fe, In, Mn, Pb, Ta, V, Y and four short irradiations for foils: Cu, Fe, In, Ta, V, W, Y. The foils were irradiated in a sandwich configuration, sorted by cross-section where the materials with higher cross-section were placed in the back of the sandwich. Neutrons produced in the p + Li-7 reaction have a quasi mono-energetic spectrum which provides a suitable basis for cross-section determination. Experimental results were calculated for (n,xn), (n,p) and (n,α) reactions via the dosimetry foils activation method including a gamma-ray spectroscopy method. Several important spectroscopic corrections have to be applied to increase the accuracy of the obtained results, including neutron background suppression. Experimental data will be submitted to the EXFOR database.

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Section: Resultsmentioning

confidence: 99%

Cross section determination for TAD materials in quasi mono-energetic neutron spectrum from p(Li) reaction

et al. 2020

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“…Two libraries (ENDF/B-VIII.0 and JEFF-3.3) adopted two different versions of the CIELO files [11]; the third evaluation, described in detail in Ref. [66], is the one adopted by most of the rest of the libraries: ENDF/B-VII.1 [67], JEFF-3.2 [68], JENDL-4.0 [69], BROND-3.1 [70], and CENDL-3.1 [71]. A comparison of the α ratio obtained in this work and the three aforementioned evaluations is provided in Fig.…”

Section: B Comparison With Evaluated Libraries and Previous Measuremmentioning

confidence: 99%

Measurement of the α ratio and (n,γ) cross section of U235
Balibrea¹,
Cembranos²,
Cano‐Ott³
et al. 2020
Phys. Rev. C
4
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0
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We measured the neutron capture-to-fission cross-section ratio (α ratio) and the capture cross section of 235 U between 0.2 and 200 eV at the n_TOF facility at CERN. The simultaneous measurement of neutron-induced capture and fission rates was performed by means of the n_TOF BaF 2 Total Absorption Calorimeter (TAC), used for detection of γ rays, in combination with a set of micromegas detectors used as fission tagging detectors. The energy dependence of the capture cross section was obtained with help of the 6 Li(n, t) standard reaction determining the n_TOF neutron fluence; the well-known integral of the 235 U(n, f) cross section between 7.8 and 11 eV was then used for its absolute normalization. The α ratio, obtained with slightly higher statistical fluctuations, was determined directly, without need for any reference cross section. To perform the analysis of this measurement we developed a new methodology to correct the experimentally observed effect that the probabilities of detecting a fission reaction in the TAC and the micromegas detectors are not independent. The results of this work have been used in a new evaluation of 235 U performed within the scope of the Collaborative International Evaluated Library Organisation (CIELO) Project, and are consistent with the ENDF/B-VIII.0 and JEFF-3.3 capture cross sections below 4 eV and above 100 eV. However, the measured capture cross section is on average 10% larger between 4 and 100 eV.

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“…Year 1988 -The compilation of FOND-1 6 ) library was finished at the frame of designing ABBN-90 5 ) group nuclear data set.…”

Section: Fond Short Historymentioning

confidence: 99%

“…Traditionally, the basic source for the FOND library was the Russian national library of evaluated nuclear data files BROND 6 ) compiled in the Russian Center of Nuclear Data cm.…”

Section: Sources For Fond Datamentioning

confidence: 99%

FOND-2.2 – Evaluated Nuclear Data Library for Constants Sets Generation at ABBN Constants Providing System

Koscheev

Nikolaev

Tsiboulia

2002

Journal of Nuclear Science and Technology

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Library of Evaluated Neutron Data Files

Cited by 10 publications

References 0 publications

Cross section determination for TAD materials in quasi mono-energetic neutron spectrum from p(Li) reaction

Cross section determination for TAD materials in quasi mono-energetic neutron spectrum from p(Li) reaction

Measurement of the α ratio and (n,γ) cross section of U235
Balibrea¹,
Cembranos²,
Cano‐Ott³
et al. 2020
Phys. Rev. C
4
0
0
0
View full text Add to dashboard Cite

FOND-2.2 – Evaluated Nuclear Data Library for Constants Sets Generation at ABBN Constants Providing System

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Library of Evaluated Neutron Data Files

Cited by 10 publications

References 0 publications

Cross section determination for TAD materials in quasi mono-energetic neutron spectrum from p(Li) reaction

Cross section determination for TAD materials in quasi mono-energetic neutron spectrum from p(Li) reaction

Measurement of the α ratio and (n,γ) cross section of U235Balibrea1, Cembranos2, Cano‐Ott3 et al. 2020Phys. Rev. C4000View full textAdd to dashboardCite

FOND-2.2 – Evaluated Nuclear Data Library for Constants Sets Generation at ABBN Constants Providing System

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Measurement of the α ratio and (n,γ) cross section of U235
Balibrea¹,
Cembranos²,
Cano‐Ott³
et al. 2020
Phys. Rev. C
4
0
0
0
View full text Add to dashboard Cite