Nuclear Data from AMS &amp; Nuclear Data for AMS – some examples

Wallner, A.; Bichler, Max; Belgya, T.; Buczak, K.; Dillmann, I.; Forstner, O.; Golser, Robin; Käppeler, F.; Klix, A.; Korschinek, G.; Krása, A.; Kutschera, W.; Lederer, C.; Mengoni, A.; Paul, M.; Plompen, A.; Priller, Alfred; Semkova, V.; Steier, Peter

doi:10.1051/epjconf/20123501003

Cited by 3 publications

(3 citation statements)

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“…The AMS measurements were performed at the Vienna environmental research accelerator (VERA) laboratory at the University of Vienna [13,17,32]. Negative uranium (plutonium)-oxide ions were extracted from the ion source, energy and mass analyzed and injected into a tandem accelerator.…”

Section: Fig 1 (Color Onlinementioning

confidence: 99%

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Novel Method to Study Neutron Capture ofU235andU
Wallner
¹
,
Belgya
²
,
Bichler
³

et al. 2014
Phys. Rev. Lett.
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37
4
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0
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The neutron capture cross sections of the main uranium isotopes, (235)U and (238)U, were measured simultaneously for keV energies, for the first time by combining activation technique and atom counting of the reaction products using accelerator mass spectrometry. New data, with a precision of 3%-5%, were obtained from mg-sized natural uranium samples for neutron energies with an equivalent Maxwell-Boltzmann distribution of kT ∼ 25 keV and for a broad energy distribution peaking at 426 keV. The cross-section ratio of (235)U(n,γ)/(238)U(n,γ) can be deduced in accelerator mass spectrometry directly from the atom ratio of the reaction products (236)U/(239)U, independent of any fluence normalization. Our results confirm the values at the lower band of existing data. They serve as important anchor points to resolve present discrepancies in nuclear data libraries as well as for the normalization of cross-section data used in the nuclear astrophysics community for s-process studies.

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Section: Fig 1 (Color Onlinementioning

confidence: 99%

“…The ionization chamber was used to separate particles of identical magnetic and electrostatic rigidity but of different energies. VERA represents one of the most sensitive facilities for such experiments and is routinely used for actinide measurements [13,17,32].…”

Section: Fig 1 (Color Onlinementioning

confidence: 99%

Novel Method to Study Neutron Capture ofU235andU
Wallner
¹
,
Belgya
²
,
Bichler
³

et al. 2014
Phys. Rev. Lett.
Self Cite
37
4
24
0
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show abstract

“…The estimated SPA for such reactions are in the range 0.1-100 b [4] and become unacceptable for the traditional activation technique. An accelerator mass th ISRD spectrometry [17] could be an alternative method due to its high sensitivity and the possibility to accumulate stable or long-lived isotopes.…”

Section: Epj Web Of Conferencesmentioning

confidence: 99%

Validation of IRDFF in²⁵²Cf Standard and IRDF-2002 Reference Neutron Fields

Simakov

Capote

Greenwood

et al. 2016

EPJ Web of Conferences

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Abstract.The results of validation of the latest release of International Reactor Dosimetry and Fusion File, IRDFF-1.03, in the standard 252 Cf(s.f.) and reference 235 U(n th ,f) neutron benchmark fields are presented. The spectrum-averaged cross sections were shown to confirm IRDFF-1.03 in the 252 Cf standard spontaneous fission spectrum; that was not the case for the current recommended spectra for 235 U(n th ,f). IRDFF was also validated in the spectra of the research reactor facilities ISNF, Sigma-Sigma and YAYOI, which are available in the IRDF-2002 collection. The ISNF facility was re-simulated to remove unphysical oscillations in the spectrum. IRDFF-1.03 was shown to reproduce reasonably well the spectrum-averaged data measured in these fields except for the case of YAYOI.

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Investigation of the excitation functions for the (n, 2n) reactions on the structural fusion material ^{58,60 – 62,64}Ni

Baldik

Yılmaz

2018

Kerntechnik

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The theoretical prediction of the cross-sections in the determination of the structure materials used in the fission and fusion technology is very important in terms of reactor safety. Also, theoretical cross-sections are necessary to evaluate the performance of structure materials, especially, in the lack or absence of experimental data. Nickel base alloys are one of the wide ranges of structural materials used in fission and fusion reactors. Therefore, the excitation functions of the (n, 2n) reactions on the structure material nickel with neutrons producing via fusion reactions are investigated in this study. Thus, the excitation functions for 58,60 – 62,64Ni(n, 2n) reactions are calculated using some pre-equilibrium models which are the hybrid, the geometry depended hybrid and the two-component excitation models. The calculations are performed in the ALICE/ASH and the Talys 1.8 codes. Also, the equilibrium and pre-equilibrium effects on these reactions are investigated in this study. The obtained cross-sections are discussed and compared with the experimental data and the theoretical predicted data.

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Nuclear Data from AMS & Nuclear Data for AMS – some examples

Cited by 3 publications

References 50 publications

Novel Method to Study Neutron Capture ofU235andU
Wallner
¹
,
Belgya
²
,
Bichler
³

et al. 2014
Phys. Rev. Lett.
Self Cite
37
4
24
0
View full text Add to dashboard Cite

Novel Method to Study Neutron Capture ofU235andU
Wallner
¹
,
Belgya
²
,
Bichler
³

et al. 2014
Phys. Rev. Lett.
Self Cite
37
4
24
0
View full text Add to dashboard Cite

Validation of IRDFF in²⁵²Cf Standard and IRDF-2002 Reference Neutron Fields

Investigation of the excitation functions for the (n, 2n) reactions on the structural fusion material ^{58,60 – 62,64}Ni

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Nuclear Data from AMS & Nuclear Data for AMS – some examples

Cited by 3 publications

References 50 publications

Novel Method to Study Neutron Capture ofU235andUWallner1, Belgya2, Bichler3 et al. 2014Phys. Rev. Lett.Self Cite374240View full textAdd to dashboardCite

Novel Method to Study Neutron Capture ofU235andUWallner1, Belgya2, Bichler3 et al. 2014Phys. Rev. Lett.Self Cite374240View full textAdd to dashboardCite

Validation of IRDFF in252Cf Standard and IRDF-2002 Reference Neutron Fields

Investigation of the excitation functions for the (n, 2n) reactions on the structural fusion material 58,60 – 62,64Ni

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Product

Resources

About

Novel Method to Study Neutron Capture ofU235andU
Wallner
¹
,
Belgya
²
,
Bichler
³

et al. 2014
Phys. Rev. Lett.
Self Cite
37
4
24
0
View full text Add to dashboard Cite

Novel Method to Study Neutron Capture ofU235andU
Wallner
¹
,
Belgya
²
,
Bichler
³

et al. 2014
Phys. Rev. Lett.
Self Cite
37
4
24
0
View full text Add to dashboard Cite

Validation of IRDFF in²⁵²Cf Standard and IRDF-2002 Reference Neutron Fields

Investigation of the excitation functions for the (n, 2n) reactions on the structural fusion material ^{58,60 – 62,64}Ni