Validated thermal-hydraulic calculation methods are essential for safety assessments of nuclear reactors, since experiments are at least expensive and mostly impossible or undesirable. In the framework of the validation of thermal-hydraulic codes for liquid metal-cooled pool-type reactor applications, the end-of-life dissymmetric test performed in the Phénix sodium reactor was selected to carry out a benchmark activity. This paper covers the achievements of the multiscale models on the simulation of this benchmark.The Phénix sodium-cooled fast reactor contains two pools in which characteristic 3D effects like thermal stratification and jets play a significant role. One of the two active heat exchanger sets fails in the dissymmetric test, leading to changes in the thermal stratification and asymmetric conditions in the reactor. Therefore 3D modelling using Computational Fluid Dynamics codes (CFD) is required to model this transient in sufficient detail. However, several aspects of the reactor, like the core and the secondary side of the heat exchanger, can be modelled more efficiently by System Thermal-Hydraulics codes (STH). Therefore multiscale models are developed by coupling CFD and STH codes, exploiting the strengths of both codes in terms of modelling options and computational costs. The results provide insight in the local flow patterns and the temperature distribution during the dissymmetric transient. The results and modelling choices of the participants are compared in this paper and the main findings are discussed in the light of lessons learned from the blind phase of the benchmark and providing recommendations for future modelling of pool-type liquid metal-cooled reactors.