Progress in the development of the neutron flux monitoring system of the French GEN-IV SFR: Simulations and experimental validations

Abstract

The neutron flux monitoring system of the French GEN-IV sodium-cooled fast reactor will rely on high-temperature 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.