The main phases in the development of the constants required for neutron-physical calculations of fast reactors, ranging from systems of BNAB group constants to modern national libraries of the BROND and ROSFOND evaluated nuclear data files, are examined. Problems for subsequent conversion of the libraries into licensed sets of standard data for nuclear technological projects are formulated.Nuclear data are the foundation of the physical concepts of the technologies devised for different purposes. The fundamental practical aspects of the designs depend on the reliability and completeness of these data: nuclear and radiation safety, economic desirability and environmental acceptability. The entire volume of data can be described if the facts that about 1000 stable and radioactive nuclides have been drawn into the nuclear technologies and the neutron energy range extends from thermal to tens-hundreds MeV -are taken into account.The recommended evaluated data based on the complete global set of experimental and theoretical values are used in the implementation of nuclear technologies. Each country creates national or regional libraries of evaluated nuclear data based on the global data set accumulated thus far: BROND, ROSFOND (Russia), ENDF/B (USA), JEFF (Europe), JENDL (Japan), and CENDL (China). All libraries are continually updated, which leads to the development of new versions. In the future, it will be possible to develop an international library of evaluated nuclear data by picking the best files from the national libraries, such as FENDL, which was formed in 1995 for the ITER project.In Russia, the BNAB-93 system of constants [1], which is based on the FOND-2 compilation of neutron data [2], is primarily used in engineering calculations of fast reactors. With the aid of the constants preparation program CONSYST [3] and a set of interface modules, the BNAB-93 system a large number of integrated experiments performed on the BFS stand and many foreign stands and on the power reactors BN-350, BOR-60, BN-600 and Superphenix (France) and it was tested on many international computational benchmark experiments. The latest version of this system makes it possible to evaluate their error due to the inaccuracies in the constants used while at the same time calculating the neutron-physical characteristics of reactors. The BN-1200, BREST, SVBR, SEFR and MBIR designs were developed on the basis of the system BNAB-93-CONSYST. Aside from the neutron and photon constants, BNAB-93 also includes the yield of fission products and data on the decay characteristics as well as radionuclides formed in other neutron reactions.