The average number of neutrons ?eff emitted by the isotopes U233, U235 and Pu239 on capture of neutrons with energies from 30 to 900 key

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

“…For the fission cross section, the values recommended in the 2018 Fig. 3 235 U fission and capture cross sections calculated for JEFF- 3.3 with TALYS (E < 100 keV), compared with fission cross sections reported in Refs [40] (IAEA 2006) and [33] (nTOF 2015) and with capture data retrieved from the EXFOR data base: [45] (Andreev), [46,47] (Corvi) [48] (Hopkins), [49] (Kononov) [50] (Muradyan), [51] (Spivak) neutron standards file [40], were used. Capture cross section data in the EXFOR data base are characterised by a large spread.…”

“…The isotope is unstable, but has a half-life of 76,000 years and is produced in thermal neutron spectra from neutron capture in 58 Ni. For austenitic materials, including a wide range of common stainless steels, nickel may be sufficiently transmuted to reach as much as 3% of the nickel content and 59 Ni reactions have been shown to contribute the vast majority of displacement damage in some Left: The 52 Cr(n,2n) 51 Cr and 52 Cr(n,p) 52 V evaluations compared with the experimental data. Middle: The production of protons (left) and alphas (right) on natural chromium.…”

“…The 111 stable nuclide evaluations from TENDL adopted in the JEFF-3.3 neutron sub-library Nuclides 17,18 O, 20,21,22 Ne, 31 P, 32,33,34,36 S, 36,38 Ar, 39,41 K, 40,42,43,44,46 Ca, 45 Sc, 46−50 Ti, 51 V, 64,[66][67][68]70 Zn 69,71 Ga, 75 As, 74,[76][77][78]80 Se, 79,81 Br, 80,[82][83][84]86 Kr, 85 Rb, 84,86−88 Sr, 93 Nb, 100,101 Ru, 102,110 Pd, 107 Ag, 122,124 Sn, 120,…”