Few examples of calculated uncertainties (in pcm) in [34] from covariance files. 

Few examples of calculated uncertainties (in pcm) in [34] from covariance files. 

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The challenge for any nuclear data evaluation project is to periodically release a revised, fully consistent and complete library, with all needed data and covariances, and ensure that it is robust and reliable for a variety of applications. Within an evaluation effort, benchmarking activities play an important role in validating proposed libraries...

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... and JENDL-4.0 are tested in the NEA criticality validation suite. As it was expected, large differences in keff uncertainties were found due to 239 Pu and 235 U covariance data in JEFF-3.3.T1 (see Table 2). Sensitivity and uncertainty analysis for the Tritium Breeding Ratio (TBR) of a DEMO Fusion Reactor was carried out with different sets of covariance data: JEFF-3.2, ...

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Citations

... Other evaluations used in this paper, i.e., the JEFF-3.3 [31] or the ENDF/B-VII.1 [32] evaluations, were based on the Los Alamos or Madland-Nix model [33]. ...
... The transport files employed in the transport and correction calculations were taken from the ENDF/B-VII.I library [32] except for 235 U which was taken alternatively from ENDF/B-VIII.0 library [26], ENDF/B-VII.1 library, or JEFF-3.3 [31] to show major differences in evaluated prompt fission thermal-neutron spectrum. ENDF/B-VII.I library was chosen for transport because of consistency with older calculations before the release of the ENDF/B-VIII.0 ...
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... and JEFF-3.2 [[5], [6], [7], [8], [9]], and to compare the results with the references. The OECD/NEA Expert Group proposed the VVER-1000 LEU and MOX assembly computational benchmark as a theoretical benchmark for investigating the physics of a whole VVER-1000 reactor core using two-thirds (LEU) and one-third (MOX) fuel [ [10], [11]]. ...
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... The black (solid), orange (dashed), pink (dotted), blue (dash-dotted), and green (densely dashed) lines, respectively, denote CENDL-3.2 [19], ENDF/B-VIII.0, JEFF3.3 [20], BROND-3.1 [21], and JENDL-4.0HE evaluations. ...
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... Figure 5(a) shows the presented FPY results and total uncertainties along with the evaluated nuclear data and experimental data in Table 2. Figure 5(b) shows that the majority of discrepancies between evaluations ENDF/B-VIII.0 [29] and JEFF-3.3 [30] are 0.1% -40%. ...
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... However, ENDF/B-VIII.0[19] and JEFF-3.3[20] have their own dedicated decay libraries. ...
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... In the Evaluated Nuclear Data File (ENDF; Trkov and Brown, 2018), thermal neutron scattering in an atomic system is explained using the thermal scattering law (TSL), which is the fundamental data to evaluate thermal scattering cross-sections. Currently, individual TSL data files are contained in the major ENDF such as ENDF/B , JEFF (Cabellos et al., 2017), and JENDL (Shibata et al., 2011). However, a limited number of materials have TSL data. ...
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... 2018), JEFF-3.3(Cabellos et al., 2017), JENDL-4.0(Shibata et al., 2011),CENDL-3.1Ge et al., 2011, ROSFOND-2010(Zabrodskaya et al., 2007,EAF-2010 (Packer andSublet, 2010), TENDL-2017Koning andRochman, 2012 and IRDFF-II Trkov et al., 2020nuclear data libraries for comparison. The input 252 Cf(sf) neutron spectrum was taken from the IAEA IRDFF webpage. There is a possibility to ...
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... without further change. A summary of benchmarking and validation activities for the first test releases of JEFF-3.3 can be found in Reference [368]. ...
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The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutron-induced interactions with the major actinides \(^{235}\hbox {U}\), \(^{238}\hbox {U}\) and \(^{239}\hbox {Pu}\), on \(^{241}\hbox {Am}\) and \(^{23}\hbox {Na}\), \(^{59}\hbox {Ni}\), Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yields, 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 for the evaluations. 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 performes very well for a wide range of nuclear technology applications, in particular nuclear energy.