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Plompen, A. J. M.*; Cabellos, O.*; De Saint Jean, C.*; Fleming, M.*; Algora, A.*; Angelone, M.*; Archier, P.*; Bauge, E.*; Bersillon, O.*; Blokhin, A.*; et al.
European Physical Journal A, 56(7), p.181_1 - 181_108, 2020/07
Times Cited Count:331 Percentile:99.41(Physics, Nuclear)The Joint Evaluated Fission and Fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides U, U and Pu, on Am and Na, Ni, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yileds, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 is excellent for a wide range of nuclear technology applications, in particular nuclear energy.
erovnik, G.*; Schillebeeckx, P.*; Becker, B.*; Fiorito, L.*; Harada, Hideo; Kopecky, S.*; Radulovic, V.*; Sano, Tadafumi*
Nuclear Instruments and Methods in Physics Research A, 877, p.300 - 313, 2018/01
Times Cited Count:5 Percentile:45.24(Instruments & Instrumentation)Methodologies to derive cross section data from spectrum integrated reaction rates were studied. The Westcott convention and some of its approximations were considered. The accuracy of the results strongly depends on the assumptions that are made about the neutron energy distribution, which is mostly parameterised as a sum of a thermal and an epi-thermal component. Resonance integrals derived from such data can be strongly biased. When the energy dependence of the cross section is known and information about the neutron energy distribution is available, a method to correct for a bias on the cross section at thermal energy is proposed. Reactor activation measurements to determine the thermal Am(n, ) cross section reported in the literature were reviewed, where the results were corrected to account for possible biases. These data combined with results of time-of-flight measurements give a capture cross section 720 (14) b for Am(n, ) at thermal energy.
erovnik, G.*; Schillebeeckx, P.*; Cano-Ott, D.*; Jandel, M.*; Hori, Junichi*; Kimura, Atsushi; Rossbach, M.*; Letourneau, A.*; Noguere, G.*; Leconte, P.*; et al.
EPJ Web of Conferences, 146, p.11035_1 - 11035_4, 2017/09
Times Cited Count:3 Percentile:85.84(Nuclear Science & Technology)erovnik, G.*; Becker, B.*; Belgya, T.*; Genreith, C.*; Harada, Hideo; Kopecky, S.*; Radulovi, V.*; Sano, Tadafumi*; Schillebeeckx, P.*; Trkov, A.*
Nuclear Instruments and Methods in Physics Research A, 799, p.29 - 36, 2015/11
Times Cited Count:4 Percentile:32.74(Instruments & Instrumentation)The methodology to derive cross section data from measurements in a cold neutron beam was studied. Mostly, capture cross sections at thermal energy are derived relative to a standard cross section, and proportionality between the standard and the measured cross section is often assumed. Due to this assumption the derived capture cross section at thermal energy can be biased by more than 10%. Evidently the bias depends on how much the energy dependence of the cross section deviates from a direct proportionality with the inverse of the neutron speed. The effect is reduced in case the cross section is not derived at thermal energy but at an energy close to the average energy of the cold neutron beam. Nevertheless, it is demonstrated that the bias can only be avoided in case the energy dependence of the cross section is known and proper correction factors are applied. In some cases the results can also be biased when the attenuation of the neutron beam within the sample is neglected in the analysis. Some of the cross section data reported in the literature suffer from such bias effects.