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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：493 Percentile：98.82(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.
Kwon, Saerom*; Konno, Chikara; Ota, Masayuki*; Sato, Satoshi*
no journal, ,
Our analyses of JAEA/FNS copper benchmark experiment with ENDF/B-VIII.0 and JEFF-3.3 pointed out that the calculation with ENDF/B-VIII.0 underestimated and that with JEFF-3.3 overestimated the measured reaction rate of the 
Nb(n,2n)
Nb sensitive to neutrons above 10 MeV. As a result of our detailed study, we specified that this issue was due to the (n,np) and (n,n') reaction data above a few MeV, etc.
Kwon, Saerom*; Konno, Chikara; Honda, Shogo*; Sato, Satoshi*; Masuda, Kai*
no journal, ,
We examined the accuracy of the iron data in the latest nuclear data libraries (FENDL-3.2b, JENDL-5, ENDF/B-VIII.0 and JEFF-3.3) used in the fusion neutron source design by using QST/TIARA iron experiment with quasi mono-energy neutrons of 40 and 65 MeV and JAEA/FNS iron experiment with DT neutrons. Then we have found the following issues on FENDL-3.2b iron data and specified that the non-elastic, inelastic scattering, (n,2n) reaction and (n,np) reaction data of 
Fe and inelastic scattering data of 
Fe caused the issues.1) The calculation results with FENDL-3.2b underestimate the measured neutron fluxes of the continuous energy range (10-60 MeV) by a factor of 0.6 in the TIARA experiment with 65 MeV neutrons. 2) The calculation results with FENDL-3.2b tend to underestimate the measured neutron flux above 10 MeV by a factor of 0.8 at depth of 70 cm and overestimate the measured ones below 10 keV by a factor of 1.3 up to depth of 40 cm in the FNS experiment.
