ABSTRACT
Nuclear science and engineering requires the availability of reliable nuclear cross section data. This chapter shows how nuclear cross section libraries with more than one energy group can be derived from raw nuclear data. Libraries of nuclear cross sections can be found on the Internet and these libraries can be accessed with a standard web browser. The quantity of a material, its microscopic cross sections, and the value of the neutron flux are all that is needed to calculate the reaction rates for any common nuclear material. The process of collapsing the fine group cross sections into the coarse group cross sections can be easily automated with a digital computer. The chapter explains the fission, absorption, scattering, and total microscopic and macroscopic cross sections for all common nuclear materials were stored in Enumerated Nuclear Data File (ENDF). The ENDF/B cross section library usually contains much more data than the designer of a nuclear power plant ever needs.
