Verification of Neutron Data for Main Reactor Materials from RUSFOND Library based on Integral Experiments

Abstract

In this work the modern state of the library of evaluated nuclear data files RUSFOND for the main reactor materials, U235, U238, Pu239, Fe, Cr, Ni, Na, Pb, etc., is given. Calculations are performed and comparison with experimental data is done for the following characteristics: (i) Removal cross-sections under the threshold of fission of U-238 etc… (ii) Average cross-sections with different standard neutron fission spectra; (iii) Criticality of fast uranium and plutonium systems. Calculations are performed using continuous energy cross-sections and a Monte-Carlo code.