JEFF-4.0 Evaluated Data: neutron induced fission products yields

Evaluated data associated to JEFF-4.0 nuclear data library: neutron induced fission product yields.

The JEFF-4.0 fission yields sub-library is an extension of the JEFF-3.3 fission yields sub-library with new evaluations of the U-233, U-235, Pu-239, and Pu-241 thermal neutron-induced fission yields. These four thermal neutron-induced fission yields were evaluated following a completely new methodology including new measurements at the Lohengrin spectrometer and a careful treatment of the full experimental database. The changes introduced in JEFF-4.0 sub-library have proven critical for improved burn-up calculations and spent fuel characterisation.