MENDF—A Code for Calculating Nuclear Data of Fission Nuclei below 200 MeV
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Abstract
Based on the spherical optical model, preequilibrium and HauserFeshbach 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 mediumlow 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 ENDF6 formatted files for the mediumlow energy region in China.
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