In recent years, the French Technical Safety Organization (IRSN) has developed a new project to simulate accurately the interaction between neutronics and thermal-hydraulic phenomena. This project, called the Advanced Neutronics and Thermal-hydraulic for the Analysis of the Reactor Safety (ANTARES), couples the thermal-hydraulic code CATHARE-3 with the three-dimensional neutronics nodal code PARCS. Following the recent reorganization of nuclear safety in France, this project is now led by French Authority for Nuclear Safety and Radiation Protection (ASNR). The aim is to provide ASNR with a multiphysics computing tool for carrying out safety analyses primarily for pressurized water reactors. To increase the reliability of ANTARES, IRSN has decided to participate in the TVA Watts Bar Unit 1 Multi-Physics Multi-Cycle Depletion benchmark proposed and supported within the framework of the Organisation for Economic Co-operation and Development/Nuclear Energy Agency Working Party on Scientific Issues of Reactor Systems working group. After a brief description of the ANTARES computational chain, this paper presents our first results, which demonstrate a good agreement between ANTARES and the proposed reference solutions by the benchmark team.