International Evaluation of Neutron Cross Section Standards

Carlson, A.D.; Pronyaev, V.G.; Smith, Donald L.; Larson, N. M.; Chen, Zhenpeng; Hale, Gerald M.; Hambsch, F. J.; Gai, E.V.; Oh, Seung-Min; Badikov, Sergey; Kawano, Toshihiko; Hofmann, H.M.; Vonach, H.; Tagesen, S.

doi:10.1016/j.nds.2009.11.001

Cited by 264 publications

(272 citation statements)

References 52 publications

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“…The 197 Au(n,γ ) cross section is an established cross-section standard for thermal neutron energies (at 0.0253 eV) and for the energy range between 0.2 and 2.8 MeV [1]. The evaluation of the standard cross section is based on available experimental data, including absolute measurements and information from relative measurements and from measurements of cross-section ratios.…”

Section: Motivationmentioning

confidence: 99%

Au197(n,γ) cross section in the unresolved resonance region

Lederer¹,

Colonna²,

Domingo‐Pardo³

et al. 2011

Phys. Rev. C

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Section: Motivationmentioning

confidence: 99%

Au197(n,γ) cross section in the unresolved resonance region

Lederer¹,

Colonna²,

Domingo‐Pardo³

et al. 2011

Phys. Rev. C

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“…The 241 Am(n, f ) cross-section has been extracted relative to the 235 U(n, f ) cross-section, which is an established standard in the neutron energy range from 150 keV to 200 MeV [25]. Compared to a direct measurement, the ratio method has the advantage that systematic uncertainties are strongly reduced, especially with respect to the determination of the neutron flux.…”

Section: Discussionmentioning

confidence: 99%

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

et al. 2013

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Abstract. The neutron-induced fission cross-section of 241 Am has been measured relative to the standard fission cross-section of 235 U between 0.5 and 20 MeV. The experiment was performed at the CERN n TOF facility. Fission fragments were detected by a fast ionization chamber by discriminating against the α-particles from the high radioactivity of the samples. The high instantaneous neutron flux and the low background of the n TOF facility enabled us to obtain uncertainties of ≈ 5%. With the present results it was possible to resolve discrepancies between previous data sets and to confirm current evaluations, thus providing important information for design studies of future reactors with improved fuel burn-up.

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“…Yields were corrected for neutron attenuation and multiple scattering in the sample using Monte Carlo methods. Absolute normalization of the cross sections were determined by measuring n-p scattering [2,3]. Representative (n,n) angular distributions are shown in Sec.…”

Section: Measurementsmentioning

confidence: 99%

Differential Cross Sections for Neutron Elastic and Inelastic Scattering on²³Na

Vanhoy

Hicks

Chakraborty

et al. 2014

EPJ Web of Conferences

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Abstract. Measurements of neutron elastic and inelastic scattering from 23 Na have been performed for sixteen incident neutron energies above 1.5 MeV with the 7-MV University of Kentucky Accelerator using the 3 H(p,n) reaction as the neutron source. These measurements were complemented by γ-ray excitation functions using the (n,n'γ) reaction. The time-of-flight technique is employed for background reduction in both neutron and γ-ray measurements and for determining the energy of the scattered neutrons. Cross section determinations support fuel cycle and structural materials research and development. Previous reaction model evaluations [1] relied primarily on total cross sections and four (n,n0) and (n,n1) angular distributions in the En = 5 to 9 MeV range. The inclusion of more inelastic channels at lower neutron energies provides additional information on direct couplings between elastic and inelastic scattering as a function of angular momentum transfer. Reaction model calculations examining direct collective and statistical properties were performed.

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International Evaluation of Neutron Cross Section Standards

Cited by 264 publications

References 52 publications

Au197(n,γ) cross section in the unresolved resonance region

Au197(n,γ) cross section in the unresolved resonance region

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

Differential Cross Sections for Neutron Elastic and Inelastic Scattering on²³Na

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International Evaluation of Neutron Cross Section Standards

Cited by 264 publications

References 52 publications

Au197(n,γ) cross section in the unresolved resonance region

Au197(n,γ) cross section in the unresolved resonance region

Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF

Differential Cross Sections for Neutron Elastic and Inelastic Scattering on23Na

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Product

Resources

About

Differential Cross Sections for Neutron Elastic and Inelastic Scattering on²³Na