MENDF—A Code for Calculating Nuclear Data of Fission Nuclei below 200 MeV

Key words: 
• MENDF program /
• fission /
• nuclear reaction /
• nuclear data

Abstract: Based on the spherical optical model, preequilibrium and HauserFeshbach statistical theory, the code MENDF (Medium Energy Nuclear Data for Fission) is written to calculate a complete set of nuclear data for fission nuclei in the mediumlow energy region (≤200 MeV). For neutron and proton induced reactions below 200 MeV, the total cross sections, reaction cross sections, elastic scattering differential cross sections, fission cross section, energy spectra of fission neutron and five kinds of emitting particles, etc. are calculated by MENDF. The calculated data generally agree with their corresponding experimental data. MENDF is widely used for nuclear data calculation and to establish ENDF6 formatted files for the mediumlow energy region in China.