Fuel Cycle interfaces with the ASTRID core

Abstract

International audienceSince 2010, CEA (French Alternative Energies and Atomic Energy Commission) and industrial partners have worked on ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project to design an innovative GEN IV Sodium Fast Reactor with a high level of requirements. At the start of the Basic Design phase, in 2016, different performance phases of the core have been defined on the life of ASTRID in particular to demonstrate the capability to recycle plutonium coming from the treatment of UOX and MOX fuels from PWRs and also the MOX coming from ASTRID itself. The objectives of these phases are to increase the burn up with using different fuel pin claddings from 90 to 150 displacements per atom (dpa). After a presentation of the innovative CFV core (low void sodium worth) and the different type of subassemblies, the paper presents some core performances and the fuel cycle needs (uranium, plutonium, B4C) on the different equilibrium phases of the core; we mention the phases to enhance performances, experimental programs for the envisaged claddings, the gradual introduction of Pu ex MOX-PWR, the experimental programs (transmutation, breeding ratio, plutonium burn up) in support to demonstrate these options for the commercial Sodium Fast Reactor. The paper shows the interfaces between the reactor and the different steps of the cycle from the front of the cycle (fabrication), the subassemblies management on ASTRID, to the back end (fuel treatment, wastes management)