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The neutron flux monitoring system of the French GEN-IV sodium-cooled fast reactor will rely on hightemperature fission chambers installed in the reactor vessel and capable of operating over a wide-range neutron flux. The definition of such a system is presented and the technological solutions are justified with the use of simulation and experimental results. I. INTRODUCTION RANCE has a long experience of about 50 years in designing, building and operating sodium-cooled fast reactors (SFR) such as RAPSODIE, PHENIX and SUPER PHENIX. Fast reactors feature the double capability of both reducing nuclear waste and saving nuclear energy resources by burning actinides. Since this reactor type is one of those selected by the Generation IV International Forum, the French government asked, in the year 2006, CEA, namely the French Alternative Energies and Atomic Energy Commission, to lead the development of an innovative GEN-IV nuclear-fission power demonstrator. The major objective is to improve the safety and availability of an SFR. In this paper, we show that the architecture of the neutron flux monitoring (NFM) system will rely on in-vessel hightemperature fission chambers (HTFC) featuring wide-range