Benchmark analyses of sodium natural convection in the upper plenum of the Monju Reactor Vessel

This publication documents the main achievements and results of the benchmark analyses performed during an IAEA coordinated research project (CRP). The goal of the CRP was to improve analytical capabilities in the field of reactor vessel thermal hydraulics in sodiumcooled fastreactors (SFRs). The CRP benefitted from the experimental data concerning a turbine trip transient test conducted in 1995 on the Monju SFR, provided by the Japan Atomic Energy Agency.