The joint evaluated fission and fusion nuclear data library, JEFF-3.3

Abstract

The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutroninduced interactions with the major actinides 235 U, 238 U and 239 Pu, on 241 Am and 23 Na, 59 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.

Nuclear data activities of the EUROfusion consortium

“…The data evaluations provided with these activities are fed into the JEFF (Joint Evaluated Fission and Fusion) nuclear data libraries, maintained and disseminated by the NEA Data Bank of the OECD, Paris [3]. JEFF addresses the needs of the European nuclear fusion and fission communities and serves, among others, as reference data library for PPPT nuclear analyses.…”

Use of shielding integral benchmark archive and database for nucleardata validation

“…), in particular concerning the evaluation of experimental sources of uncertainty. [9] and European Comission (EC) projects such as SANDA and EU-ROfusion is likewise important in order to study and recommend the proper mathematical and physics procedures to integrate these data in the ND evaluation process and thus avoid their misuse. Several laboratories from US (LLNL, ORNL) China (FDS, CIAE), Russia (IPPE) and others expressed interest in this activity.…”

Measurement of temperature-dependent thermal neutron spectrum in CaH2 moderator material for space reactor

“…The calculation of the thermal neutron spectrum in the CaH 2 at a room temperature 294 k, 392 K and 565 K was performed by a Monte-Carlo simulation code MCNP-6.2 [3] with the evaluated cross sections in the JEFF-3.3 [6]. Additionally, JEFF-3.2 thermal scattering law S(α,β) of CaH 2 at 293 K, 400 K and 600 K was used in the calculation.The heater and calculational geometry are shown in Figure 3 and Figure 4.…”