NUCLEAR DATA FOR REACTOR NEUTRONICS CALCULATIONS - ROSFOND DATA LIBRARY AND ABBN-RF GROUP DATA SYSTEM

The work is devoted to one of the most important scientific and technical problems in reactor physics related to the development and verification of codes and nuclear data that provide reliable and highly accurate calculations of neutron-physical characteristics of fast reactors and radiation shielding, including nuclear fuel cycle, criticality and radiation safety parameters. The designed neutronics characteristics of fast reactors should be based on certified, qualified sets of codes and nuclear constants: the calculation tools should be related to the modern state of scientific knowledge and computational techniques, and used nuclear physics constants should be adequate to the most reliable evaluations of nuclear data. In connection with rapid development of the computing engineering and all greater introduction in practice of calculation Monte Carlo codes, the methodical constituent of calculation error falls down substantially. In these terms the nuclear constant’s constituent of error of calculations becomes fully qualificatory. A situation is intensifyed by the fall-off of financing of experimental works, why in this connection the amount of fast critical stands in the world diminishes sharply. The paper consider the state of art of the constant’s providing system CONSYST/ABBN, created on the basis of the national library of neutron data files ROSFOND and libraries of multigroup constants ABBN-93 and ABBN-RF. One of the most important problems under consideration here also is the methodical and software for estimating of errors of the calculated physical characteristics. System of codes and nuclear data for reactor neutronics calculations is based on the unified methodological basis that ensures the transparency of the procedure for obtaining the data used in the calculations, the reliability of their verification and the obtaining of guaranteed accuracy of the calculated physical reactor characteristics.