Analysis of the KALIMER-600 Core with Different Evaluated Nuclear Data Files

The purpose of this study is to investigate the impact of the evaluated nuclear data files on the core performance parameters of the KALIMER-600 core. The following major nuclear data libraries were compared: ENDF/B-VI.6, JENDL-3.3, JEFF-3.1 and ENDF/B-VII.0. The major revisions after the release of ENDF/B-VI.6 were an update of actinide cross-sections (MA, U-235, U-238) and revisions of structure (Zr) and coolant (Na-23) material cross-sections. Since the result of the fast reactor core analysis highly depends on the evaluated nuclear data files, a selection of the appropriate microscopic evaluated nuclear data has been recognized as very important for the core design of fast reactor. The results of the comparison with the use of different evaluated nuclear data files show that most of core performance is similar between different libraries except sodium void worth and sodium density coefficient. Large differences of sodium void and density coefficient are attributed to the revision of the sodium scattering cross section in JEFF-3.1 and U-238 inelastic scattering cross section in updated data libraries.