Updated Codes and Methods to Reduce the Calculational Uncertainties on the Reactivity Effects in Liquid Metal Cooled Fast Reactors (I32005)
The CRP, with the participation of research institutes from nine countries, contributed to improving capabilities in sodium-cooled fast reactors simulation through code verification and validation, with particular emphasis on methodologies and tools used for the calculation of reactivity coefficients in industrial-size fast reactors specifically designed for enhancing the utilization of plutonium and minor actinides.
A new TECDOC 1700 entitled 'BN-600 MOX Core Benchmark Analysis: Results from Phases 4 and 6 of a CRP on Updated Codes and Methods to Reduce the Calculational Uncertainties of the LMFR Reactivity Effects' has been recently published.
The publication documents the experience gained in a second phase of a coordinated research project aimed at the verification and validation of methods and codes for evaluating sodium-cooled fast reactors (SFR) reactivity coefficients, along with their effect on transient scenarios. The investigations dealt with two core configurations fully loaded with Mixed-Oxide (MOX; i.e. U-Pu Oxide) fuel and with MOX and Minor Actinides, designed to reduce the sodium void effect thus improving the SFR safety features.
BN-600 cross-section view of the primary circuit (courtesy Institute for Physics and Power Engineering (IPPE), Obninsk, Russian Federation):