Analysis of transition scenario from a PWR to a SFR fleet simulated with the class code

International audienceOne evolution envisaged in France for electronuclear fleets considers the deployment of ASTRID-like Sodium Fast Reactor (SFR). Fuel cycle prospective studies involving this SFR integrated into a Pressurized Water Reactor (PWR) fleet is one way to evaluate such strategies. This paper presents two scenario analysis exploring effects on in-cycle plutonium quantity and quality of ASTRID-like reactor parameters and cycle parameters such as SFR spent fuel reprocessing. On one hand, under specific conditions, cycle strategies impact ASTRID-like behavior, however, on the other hand, the fuel cycle is also strongly dependent on ASTRID-like operation