2017
DOI: 10.1051/epjconf/201714604045
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Measurement of the23Na(n,2n) cross section in235U and252Cf fission neutron spectra

Abstract: Abstract. The presented paper aims to compare the calculated and experimental reaction rates of 23 Na(n,2n) 22 Na in a well-defined reactor spectra and in the spontaneous fission spectrum of 252 Cf. The experimentally determined reaction rate, derived using gamma spectroscopy of irradiated NaF sample, is used for average cross section determination.Estimation of this cross-section is important as it is included in International Reactor Dosimetry and Fusion File and is also relevant to the correct estimation of… Show more

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Cited by 2 publications
(1 citation statement)
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“…Simulation of the experiment was performed in the MCNP6.2 code. The spectrum of the Am-Be neutron source was taken from stilbene measurement [12]. As the spectrum was measured in the energy range 1-12 MeV, a correction of neutron emission below 1 MeV was necessary.…”
Section: Oxygen Inelastic Scattering Gammamentioning
confidence: 99%
“…Simulation of the experiment was performed in the MCNP6.2 code. The spectrum of the Am-Be neutron source was taken from stilbene measurement [12]. As the spectrum was measured in the energy range 1-12 MeV, a correction of neutron emission below 1 MeV was necessary.…”
Section: Oxygen Inelastic Scattering Gammamentioning
confidence: 99%