Articles de revista
Enviaments recents
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Experimental setup and procedure for the measurement of the 7Be(n,p)7Li reaction at n_TOF
(2017-04-11)
Article
Accés obertFollowing the completion of the second neutron beam line and the related experimental area (EAR2) at the n_TOF spallation neutron source at CERN, several experiments were planned and performed. The high instantaneous neutron ... -
Measurement of the U-238(n,gamma) cross section up to 80 keV with the total absorption calorimeter at the CERN n_TOF facility
(AMER PHYSICAL SOC, 2017-12)
Article
Accés obertThe radiative capture cross section of a highly pure (99.999%), 6.125(2) grams and 9.56(5)E-4 atoms/barn areal density 238U sample has been measured with the Total Absorption Calorimeter (TAC) in the 185 m flight path at ... -
High-accuracy determination of the neutron flux in the new experimental area n_TOF-EAR2 at CERN
(2017-10-27)
Article
Accés restringit per política de l'editorialA 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 approximately 20m from ... -
Measurement of the 238 U ( n , gamma ) cross section up to 80 keV with the Total Absorption Calorimeter at the CERN n_TOF facility
(AMER PHYSICAL SOC, 2017-12-01)
Article
Accés obertThe radiative capture cross section of a highly pure (99.999%), 6.125(2) grams and 9.56(5) 10-4 atoms/barn areal density 238-U sample has been measured with the Total Absorption Calorimeter (TAC) in the 185 m flight path ... -
Recuperated versus single-recuperator re-compressed supercritical CO2 Brayton power cycles for DEMO fusion reactor based on dual coolant lithium lead blanket
(2017-12-01)
Article
Accés obertThe EUROfusion research program is currently exploring alternative solutions for a future fusion power plant with DEMO (DEMOnstration Power Plant) prototype. One of the most important issues arising from a dual coolant ... -
Beta-decay half-lives and beta-delayed neutron emission probabilities for several isotopes of Au, Hg, Tl, Pb, and Bi, beyond N = 126
(2017-06-23)
Article
Accés obertBackground: There have been measurements on roughly 230 nuclei that are beta-delayed neutron emitters. They range from 8He up to 150La. Apart from 210Tl, with a branching ratio of only 0.007%, no other neutron emitter has ... -
Conceptual design of a hybrid neutron-gamma detector for study of ß-delayed neutrons at the RIB facility of RIKEN
(2017-04-07)
Article
Accés obertThe conceptual design of the BRIKEN neutron detector at the radioactive ion beam factory (RIBF) of the RIKEN Nishina Center is reported. The BRIKEN setup is a complex system aimed at detecting heavy-ion implants, ß particles, ... -
Comparison of best-estimate plus uncertainty and conservative methodologies for a PWR MSLB analysis using a coupled 3-D neutron-kinetics/thermal-hydraulic code
(2017-05-04)
Article
Accés restringit per política de l'editorialThis paper compares the Best-Estimate Plus Uncertainty (BEPU) methodology with the Conservative Bounding methodology for design-basis-accident analysis. Calculations have been performed with TRACE [for thermal-hydraulic ... -
First evidence of multiple ß-delayed neutron emission for isotopes with A > 100
(2017-03-01)
Article
Accés obertThe beta-delayed neutron emission probability, P-n, of very neutron-rich nuclei allows us to achieve a better understanding of the nuclear structure above the neutron separation energy, S-n. The emission of neutrons can ... -
Monte Carlo simulations for the study of a moderated neutron detector
(2011-08-12)
Article
Accés obertThis work presents the Monte Carlo simulations performed with the MCNPX and GEANT4 codes for the design of a BEta deLayEd Neutron detector, BELEN-20. This detector will be used for the study of beta delayed neutron emission ... -
Code improvement and model validation for Asco-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal-hydraulic code
(2016-01-01)
Article
Accés obertThis paper provides a Best Estimate validation calculation with a coupled thermal–hydraulic and 3D neutron kinetic model for Ascó-II Nuclear Power Plant. Common NRC codes have been used for its purpose. TRACE is the code ... -
Neutron capture cross section measurement of 238U at the CERN n_TOF facility in the energy region from 1 eV to 700 keV
(AMER PHYSICAL SOC, 2017-03-10)
Article
Accés obertThe aim of this work is to provide a precise and accurate measurement of the 238U(n, gamma) reaction cross section in the energy region from 1 eV to 700 keV. This reaction is of fundamental importance for the design ...
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