ENDF
ENDF (Evaluated Nuclear Data File) is a standardized collection and file format for evaluated nuclear reaction and decay data used in science and engineering. It provides tabulated information on neutron, photon, and charged-particle interactions with nuclides, including reaction cross sections, angular distributions, energy spectra, resonance parameters, thermal scattering laws, fission yields, and radioactive decay data.
The ENDF concept originated to organize and disseminate evaluated nuclear data produced by international and national
ENDF libraries are not used directly by most applications; they are processed by utility codes (for example