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.

Abstract. Measurements were performed at the time-of-flight facility GELINA to determine the 238 U(n, γ) cross section in the resonance region. Experiments were carried out at a 12.5 and 60 m measurement station. The total energy detection principle in combination with the pulse height weighting technique was applied using C 6D6 liquid scintillators as prompt γ-ray detectors. The energy dependence of the neutron flux was measured with ionisation chambers based on the 10 B(n, α) reaction. The data were normalised to the isolated and saturated 238 U resonance at 6.67 eV. Special procedures were applied to reduce bias effects due to the weighting function, normalization, dead time and background corrections, and corrections related to the sample properties. The total uncertainty due to the weighting function, normalization, neutron flux and sample characteristics is about 1.5%. Resonance parameters were derived from a simultaneous resonance shape analysis of the GELINA capture data and transmission data obtained previously at a 42 m and 150 m station of ORELA. The parameters of resonances below 500 eV are in good agreement with those resulting from an evaluation that was adopted in the main data libraries. Between 500 eV and 1200 eV a systematic difference in the neutron width is observed. Average capture cross section data were derived from the experimental capture yield in the energy region between 3.5 keV and 90 keV. The results are in good agreement with an evaluated cross section resulting from a least squares fit to experimental data available in the literature prior to this work. The average cross section data derived in this work were parameterised in terms of average resonance parameters and included in a least squares analysis together with other experimental data reported in the literature.

Abstract. The radiation shielding calculations were performed for the beam experiment hall of the Proton Engineering Frontier Project (PEFP) in Korea using MCNPX code with nuclear data libraries of the ENDF-B/VII, JEFF3.1, LA150, JENDL-HE, and physics models, Bertini and Isabel built in MCNPX code. The neutron energy spectra from 6 targets (20 MeV/ 1.5 mA-Si, Cu, target, 20 MeV/ 50 uA-Si, 20 MeV/ 4.8 mA-C target, 100 MeV/ 300 uA-Si, W target, 100 MeV/ 10 uA-Si, 100 MeV/ 1.6 mA-C target) were calculated and used as radiation source terms. With these results, the concrete thickness satisfying shielding regulations in Korea was calculated for the target rooms and the building of the Beam Experiment Hall. Bertini, Isabel, JENDL/HE and LA150 nuclear data were applied to the evaluation of the proton induced neutrons. ENDF/B-VII, JEFF3.1, and JENDL/HE nuclear data were applied to the evaluation of the concrete shield.