JEFF-4.0 Evaluated Data: neutron induced fission products yields
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https://data.oecd-nea.org/doi/10.82555/trtwt-k2828
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资源简介:
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.
提供机构:
OECD Nuclear Energy Agency
创建时间:
2025-06-19



