Abstract
Nuclear scenario studies are performed to explore the impact of possible evolutions of nuclear fleets. The nuclear fuel cycle simulation tool COSI, developed by CEA, is used to model these dynamic scenarios and to evaluate them with respect to uranium and plutonium management, fuel reprocessing and waste production. In recent years, scenarios have focused on transitions from the current nuclear French fleet to a deployment of SFR. However, the French Multi-annual Energy Planning has recently postponed the deployment of this technology to the second half of the 21st century. Alternative solutions of plutonium management in PWR are investigated to stabilize total inventories of spent nuclear fuels. The MIX concept is based on homogeneous fuel assemblies where fuel rods are composed of plutonium blended with enriched uranium. In this study, a transition from the current French fleet to an EPR™ fleet is simulated. Two power capacities of the future EPR™ fleet are considered. A progressive deployment of fuel multi-recycling in the EPR™ fleet is implemented to enable stabilization of all spent fuels and plutonium inventories. Natural uranium consumption is also minimized thanks to ERU fuel batches in EPR™. Results are compared with plutonium and uranium mono-recycling in a PWR fleet.
Highlights
Nuclear scenario studies aim to explore possible prospective developments of nuclear fleets
MIX refers to an assembly where fuel rods are composed of Pu oxide mixed with enriched uranium oxide [8]
Transitions from the current French fleet to European Pressurized Reactors (EPR) fleets are simulated with the scenario code COSI6, within the limits of conservative criteria defined and validated with the French industry: EDF, ORANO and FRAMATOME
Summary
Nuclear scenario studies aim to explore possible prospective developments of nuclear fleets Within this framework, scenarios are designed, in France, within the limits of conservative criteria defined and validated with the French industry: EDF, ORANO and FRAMATOME. This study aims to explore trajectories involving the deployment of Pu multi-recycling in PWR À and are useful from a research and development perspective À but do not constitute the reference evolution for the French fleet to this date. Hypotheses used for those simulations are continuously upgraded in collaboration with industrial partners, as research on cycle plants and reactor designs advances. U enrichment Reprocessed uranium Separated Pu (outside fabrication plants) UOX spent fuels ERU spent fuels MOX spent fuels
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