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Article
Open AccessMeasurement of the prompt fission \(\gamma \) -rays from slow neutron-induced fission of \(^{235}\) U with STEFF
The average energy and multiplicity of prompt \(\gamma \) γ -rays from slow ...
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Article
Open Access\(^{74}\) Ge( \(n,\gamma \) ) cross section below 70 keV measured at n_TOF CERN
Neutron capture reaction cross sections on \(^{74}\) 74 ...
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Article
Open AccessHigh accuracy, high resolution 235U(n,f) cross section from n_TOF (CERN) from 18 meV to 10 keV
The 235U(n,f) cross section was measured in a wide energy range (18 meV–170 keV) at the n_TOF facility at CERN, relative to 6Li(n,t) and 10B(n,α) standard reactions, with high resolution and accuracy, with a setu...
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Article
Imaging neutron capture cross sections: i-TED proof-of-concept and future prospects based on Machine-Learning techniques
i-TED is an innovative detection system which exploits Compton imaging techniques to achieve a superior signal-to-background ratio in ( $$n,\ga...
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Article
Open AccessThe joint evaluated fission and fusion nuclear data library, JEFF-3.3
The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides \(^{235}\hbox {U}\) 235 U , \(^{238}\hbox {U}\)
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Article
Open AccessMeasurement of the 235U(n, f) cross section relative to the 6Li(n, t) and 10B(n,\( \alpha\)) standards from thermal to 170 keV neutron energy range at n_TOF
The 235U(n, f ) cross section was measured at n_TOF relative to 6Li(n, t) and 10B(n,\( \alpha\)α) , with high resolution ( \( L=183.49(2)\)L=183.49(2) m) and in a wide energy range (25meV-170keV) with 1.5% systematic...
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Article
Verification of R-matrix calculations for charged-particle reactions in the resolved resonance region for the 7Be system
R-matrix theory is used to describe nuclear reactions in the resolved resonance region. It uses information on bound states and low energy resonances to accurately parametrize cross sections on the resonances ...
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Article
Erratum to: Cross section measurements of 155, 157Gd(n,\(\gamma\)) induced by thermal and epithermal neutrons
After publication of the paper, the authors noticed some errors in the list of authors and in the list of affiliations. Their correct version is given in this erratum.
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Article
Cross section measurements of 155,157Gd(n,\(\gamma\)) induced by thermal and epithermal neutrons
Neutron capture cross section measurements on 155Gd and 157Gd were performed using the time-of-flight technique at the n_TOF facility at CERN on isotopically enriched samples. The measurements were carried out in...
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Chapter and Conference Paper
\(^{7}\) Be(n,p) \(^{7}\) Li Cross Section Measurement for the Cosmological Lithium Problem at the n \(\_\) TOF Facility at CERN
One of the most puzzling problems in Nuclear Astrophysics is the “Cosmological Lithium Problem”, i.e the discrepancy between the primordial abundance of
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Article
High-accuracy determination of the neutron flux in the new experimental area n_TOF-EAR2 at CERN
A new high flux experimental area has recently become operational at the n_TOF facility at CERN. This new measuring station, n_TOF-EAR2, is placed at the end of a vertical beam line at a distance of approximat...
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Article
Open AccessNuclear data activities at the n_TOF facility at CERN
Nuclear data in general, and neutron-induced reaction cross sections in particular, are important for a wide variety of research fields. They play a key role in the safety and criticality assessment of nuclear...
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Article
Integral measurement of the 12C(n, p)12B reaction up to 10 GeV
The integral measurement of the 12C(n, p)12B reaction was performed at the neutron time-of-flight facility n_TOF at CERN. The total number of 12B nuclei produced per neutron pulse of the n_TOF beam was determined...
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Chapter and Conference Paper
Nuclear Data for the Thorium Fuel Cycle and the Transmutation of Nuclear Waste
Neutron-induced reaction cross sections play an important role in a wide variety of research fields, ranging from stellar nucleosynthesis, the investigation of nuclear level density studies, to applications of...
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Article
High-accuracy determination of the neutron flux at n_TOF
The neutron flux of the n_TOF facility at CERN was measured, after installation of the new spallation target, with four different systems based on three neutron-converting reactions, which represent accepted c...
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Article
Open AccessPerformance of the neutron time-of-flight facility n_TOF at CERN
The neutron time-of-flight facility n_TOF features a white neutron source produced by spallation through 20GeV/c protons im**ing on a lead target. The facility, aiming primarily at the measurement of neutron-in...
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Article
Open AccessMeasurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF
The neutron-induced fission cross-section of 241Am has been measured relative to the standard fission cross-section of 235U between 0.5 and 20MeV. The experiment was performed at the CERN n_TOF facility. Fission ...
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Article
Open AccessSimultaneous measurement of neutron-induced capture and fission reactions at CERN
The measurement of the capture cross-section of fissile elements, of utmost importance for the design of innovative nuclear reactors and the management of nuclear waste, faces particular difficulties related t...
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Article
Open AccessMeasurement of the neutron-induced fission cross-section of 243Am relative to 235U from 0.5 to 20 MeV
The ratio of the neutron-induced fission cross-sections of 243Am and 235U was measured in the energy range from 0.5 to 20 MeV with uncertainties of ≈ 4%. The experiment was performed at the CERN n_TOF facility us...
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Article
Open AccessNeutron-induced fission cross-section of 233U in the energy range 0.5 < En < 20 MeV
The neutron-induced fission cross-section of 233U has been measured at the CERN n_TOF facility relative to the standard fission cross-section of 235U between 0.5 and 20MeV. The experiment was performed with a fas...
